, . ._ - _ _ _ _ _ _ _ - _ .

. .

j . -

t.

.

PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES

Big Rock Point Plant

8200:160431 820310gDRADOCK 05000155

PDR

nu0282-0028d142

- _ _ - _ _ _ _ _ _ _ _ _ _

. .

. .

60

6.3.2 Refueling Operation Controls

Interlocks shall be provided to prevent all motion with any of therefueling cranes (namely, jib cranes, transfer cask winch) whichare positioned over the reactor vessel whenever any control rod isnot fully inserted in the core and the mode selector switch is inthe " refuel" position.

6.3.3 Operating Requirements

(a) All reactor refueling safety system sensors and trip devices shallbe functionally tested at each major refueling shutdown and shallbe maintained in the specified condition during all refuelingoperations.

(b) The refueling operation controls including position interlocksshall be functionally tested at each major refueling shutdown.

6.4 PLANT MONITORING SYSTEMS

The plant monitoring systems include the process radiation monitoringsystems, the area monitoring system, and the reactor water levelmonitors in the Reactor Depressurizing System, and the containmentpressure and level monitors.

6.4.1 Process Radiation Monitoring Systems

The process radiation monitoring systems consist of the air ejectoroff-gas monitoring system including the fuel rupture detection system;stack gas monitoring system, the emergency condenser vent monitor, andprocess liquid monitor system.

(a) Air Ejector Off-Gas Monitoring Systems

Continuous monitoring of the air ejector off-gas radioactivityshall be provided by either two ion chamber type systems or two

| single-channel gamma scintillation spectrometer systems designed

| to detect noble gas fission products indicative of a fuel elementrupture. One system (either ion chamber or scintillationdetector) will always be in service with an identical system as anoperational spare. The sampling system shall be designed to holdup the gas sample to allow time for the decay of Nitrogen-16 andother short-lived activation gases. The off gas monitoringchannels shall be calibrated so that the indicated and recordedcount rate output of the channel in service, combined with theoff gas flow Permits detemination of the fission gases discharge

24rate from 10 to 10 curies per second at the stack. A tripcircuit in the air ejector off gas monitor shall have an alarmwhich shall annunciate in the control room. The air ejector off-gas monitor trip circuit shall also initiate action of a time-delay switch, which in turn shall trip the off-gas shutoff valveclosed after a preselected delay adjustable up to 15 minutes.Alarm and trip settings shall be as specified in Section 6.4.3(a).

nu0282-0026d142 Proposed

|L

..

. .

62

The radioactive waste system effluent to canal channel shall beused in conjunction with the liquid waste disposal system. Eachbatch of liquid wastes to be discharged shall be analyzed prior todischarge as described in 6.5. This monitor shall provide anadditional means of checking the activity of the wastes being

'

discharged..

The circulating water discharge monitor shall monitor the main I

stream of plant effluent prior to its discharge into LakeMichigan, and serve as a backup to the other liquid monitors. In

addition, a continuous sample is drawn from the discharge canalfor periodic analysis as specified in 6.4.3(d).

(e) In-Plant Radio-Iodine Measurements Under Accident Conditions

Procedures for determining airborne radio-iodine concentrations inoccupied areas shall be implemented and technicians shall betrained on an annual basis. Maintenance of the sampling equipmentshall occur at least semi-annually and maintenance of theanalytical equipment shall occur at least monthly.

6.4.2 Area Monitoring System, Reactor Water Level Monitors and ContainmentMonitors

(a) Nineteen fixed gamma monitors employing scintillation typedetectors shall be installed throughout the plant, and each shallhave the following:

(i) A range consistent with expected radiation levels in thearea to be monitored. (0.01 mr to 10 mr or 0.1 mr to 100 mror 1 mr to 1,000 mr.)

(ii) An output indicated and recorded in the control room.

(iii An adjustable high radiation alarm which shall beannunciated in the control room. Alarm settings that shall

be as indicated in 6.4.3(e).

(b) Two of these nineteen area monitors shall be located in thevicinity of the fuel storage areas to provide gamma monitoring ofthe fuel storage areas and refueling operations. Local alarmsshall be provided for these monitors, and alarm setting shall bein accordance with the provisions of 10 CFR 70. In the event thatboth of these monitors become inoperable during power operation orfuel handling activities, the containment ventilation isolationvalves shall be closed.

However, notwithstandi: g the requirements of Section 70.24(a)(1),alarm settings may be raised above 20 mR/hr as long as the overalldetection criterion in Section 70.24(a)(1) is satisfied and therequirements specified in paragraph 6.4.3(e) below are met.

nu0282-0026e142 Proposed

: . . - -

..

. ,

63

6.4.2 (Contd)

(c) At least five environmental film or TLD monitoring stations shallbe provided for determining the integrated gamma dose rate in thesite environs. These stations shall be placed on an arc of about1,350 meters from the stack.

(d) Four narrow ' range water level monitors are provided in the maincontrol room as part of the Reactor Depressurizing System to beused for detection of adequate core cooling during accidentsituations.

(e) Two containment pressure monitors and two containment levelmonitors are provided in the main control room for accidentmonitoring.

6.4.3 Operating Requirements

(a) At least one of the two air ejector off gas monitoring systemsshall be in service during power operation and set to initiateclosure of the off gas isolation valve as described below. Ala rmsnormally shall be set to annunicate in the control room if theoff-gas radioactivity reaches a level that corresponds to a stackrelease of 0.1 curie per second. At stack releases above 0.1curie per second, the alarm shall be set approximately a factor oftwo above the expected off gas release rate but in no event abovethat level corresponding to a stack release of 0.47/E curie persecond where E is the average gamma energy per disintegration(MEV/ dis). If the limit of 0.47/E curie per second is exceeded,reactor power shall be immediately reduced such as to meet thelimits. The monitors shall be set to initiate closure of the off-gas isolation valve (af ter a time adjustable from 0 to 15 minutes)if the off gas radioactivity reaches a level that would correspondto a stack release rate of ten curies per second. Off-gas samplesshall be taken monthly during power operation and analyzed forcalibration of the off gas radiation monitors. The automaticclosure function of the monitors shall be tested monthly duringpower operation.

(b) The stack-gas monitoring system shall normally be in service.Adequate spare parts shall be on hand to allow necessary repairsto be made promptly. The alarm normally shall be set toannunciate in the control room at a level that corresponds to astack release rate of 0.1 curie per second. At stack releaserates above 0.1 curie per second, the alarm shall be setapproximately a factor of two above the expected stack releaserate, but in no event above 0.47/E curies per second.

The calibration of the system shall be checked at least monthly.The particulate filter and iodine filter shall be analyzed atleast weekly.

(c) One of the emergency condenser vent monitors shall be in serviceat all times during power operation. The monitors shall be set toalarm at approximately 10 mr above the maximum expected backgroundduring operation of the emergency condenser. The calibrationshall be checked at least monthly.

nu0282-0026d142 Proposed

_

.. .

..

.. .

'64a

6.4.3 (Contd)

(h) Two containment pressure monitors and two containment levelmonitors shall be operable during power operation. Plant shutdownis required within 12 hours following a 7 day period when onemonitor of either type is inoperable. Plant shutdown is requiredwithin 12 hours following a 48 hour period when both monitors ofone type are inoperable.

|i

.

|

|

|

||

nul081-0016d142 Proposed

i

- , , , ,- - . _ . - - ,

.

.. .

. .

76b

7.6 (Contd)Reference Procedure

System or Function Frequency of Within TheseUndergoing Test Routine Tests Specifications

Calibration of area One month or less Section 6.4.3monitoring system

Channel comparison check One month or less Section 6.4.3of reactor level indicatinginstruments in the ReactorDepressurization System

Calibration of reactor At each major Section 6.4.3level indicating instru- refueling shutdown

ments in the reactorDepressurizing System

Steam drum safety valve One month or less Section 4.1.2position monitor check

Calibration of steam drum At each major refueling Section 4.1.2safety valve position shutdownmonitors

High radiation trip At each major refueling Section 6.4.2closure of the contain- shutdownment ventilationisolation valves

Calibration of contain- At each major Section 6.4.3ment water level monitors refueling shutdown

| and containment pressure! monitors

I

!

iili

nu0282-0026d142 Proposed

1,

. . - , - .- -.