ML18139C301

Proposed Tech Specs Adding Reactor Vessel Level Coolant Monitor to Tables 3.7-6 & 4.1-2 to Meet Requirements of NUREG-0737,Item II.F.2, Detection of Inadequate Core Cooling.

ML18139C301
Person / Time
Site:	Surry
Issue date:	03/31/1983
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18139C300	List: ML18139C299 ML18139C301
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM NUDOCS 8304110482
Download: ML18139C301 (5)

Text

---

~----6304110482 830331 PDR ADOCK 05000280 p PDR e ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE TABLE 3.7-6 ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT

1. Auxiliary Feedwater Flow Rate 2. Reactor Coolant System Subcooling Margin Monitor 3. PORV Position Indicator (Primary Detector)

4. PORV Position Indicator (Backup Detector)

s. PORV Block Valve Position Indicator

6. Safety Valve Position Indicator (Primary Detector)

7. Safety Valve Position Indicator (Backup Detector)

8. Reactor Vessel Coolant Level Monitor TOTAL NO. OF CHANNELS 1 per S/G 2 1/valve 1/valve I/valve I/valve 1/valve 2 TS 3.7-21 MINIMUM CHANNELS OPERABLE 1 per S/G 1 1/valve 0 I/valve 1/valve 0 1 1*

TS 4.1-9a TABLE 4.1-2 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument

1. Auxiliary Feedwater Flow Rate 2. Reactor Coolant System Subcooling Margin Monitor 3. PORV Position Indicator (Primary Detector)

4. PORV Position Indicator (Backup Detector)

5. PORV Block Valve Position Indicator

6. Safety Valve Position Indicator

7. Safety Valve Position Indicator (Backup Detector)

8. Reactor Vessel Coolant Level Monitor Channel Check p M M M M M M M Channel Calibration R R R R R R R R e ATTACHMENT 2 DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION CHANGE

... : ., .... \"t DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION CHANGE A Westinghouse designed, redundant microprocessor-based system to monitor reactor vessel coolant level is being installed.

The system utilizes differential press1;1re measuring transmitters which measure water level and relative void content of the circulating primary coolant system fluid and thus provides direct readings of reactor vessel coolant level. This system has been designed to meet the requirements of NUREG-0737, Item II.F.2. It will not affect normal station operation or the operation of ariy safety related equipment nor does it create an "unreviewed safety question", as defined in 10CFR50.59.

The design basis for the Reactor Vessel Coolant Level Monitoring System is Appendix B to NUREG-0737, "Design and Qualification Criteria for Accident Monitoring*

Instrumentation" as clarified in NUREG-0737, Item II.F.2. except that the equipment will not meet with Regulatory Guide 1.100 requirements of testing under seismic conditions with the equipment operating.

The Reactor Vessel Coolant Level Monitoring System does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment

• important to safety previously evaluated in the UFSAR. Reactor coolant losses resulting from a line rupture would be r.estricted by penetri;ition size to that flow which is within the makeup capability of existing ECC Systems. The system does not provide a path which would allow reactor coolant to exit the containment boundary.

The system is ,designed and constructed in accordance with the General Design Criteria 14, 15, 16, 30, and 55 of Appendix A to 10CFR50. The modification will not affect the operation nor does it revise protection or logic schemes of any equipment important to safety previously evaluated in the UFSAR. A possibility of an accident or malfunction of a different type than previously evaluated in the UFSAR is not created. This modification will neither replace any existing system nor couple with any safety system. The margin of safety as defined in the basis for any Technical Specification is not reduced. The penetration of the reactor vessel head and the . related system piping is limited in size to be within the capacity of the existing ECC Systems and a failure of this additional system (Reactor Vessel toolant Level Monitoring System) does not challenge the Safety Analysis which forms a basis for the Technical Specification~

The modification will not* affect safety systems for any postulated accidents.

The modification will, however, provide addi.tional information to the operator during accident conditions.