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Responds to Generic Ltr 87-06 Re Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves.Present Tech Spec Requirements Combined W/Sys Design Features Adequate to Detect RCS Pressure Boundary Leakage
	ML20214E349
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/15/1987
From:	Frisch R; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	GL-87-06, GL-87-6, NUDOCS 8705220050
	Download: ML20214E349 (5)
	v • d • e

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@ Consumers MN5 MISENE55 Power ro wsmuus General offices: 1945 West Parnall Road, Jackson, MI 49201 e (517) 788-0550 May 15, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

RESPONS3 TO GENERIC LETTER 87-06, PERIODIC VERIFICATION OF LEAK TIGHT INTEGRITY OF PRESSURE ISOLATION VALVES Generic Letter 87-06, Periodic Verification of Leak Tight Integrity of Pres-sure Isolation Valves, dated March 13, 1987, requests that all Licensees review methods in place for assuring the leak-tight integrity of pressure isolation valves as independent barriers against abnormal leakage, rapidly propagating failure, and gross rupture of the reactor coolant pressure boundary. Pressure isolation valves (PIVs) are defined for each interface as any two valves in series within the reactor coolant pressure boundary which separate the high pressure Reactor Coolant System (RCS) from an attached low pressure system and are normally closed during power operation. This submit-tal provides Consumers Power Company's response to the Ceneric Letter.

SEP Topic V-5, " Reactor Coolant Pressure Boundary Leakage Detection" for Big Rock Point evaluated this issue as "Intersystem Leakage Detection." As discussed in Consumers Power Company letter dated June 6, 1983, three systems interfacing with the Reactor Coolant System pressure boundary at Big Rock Point are of concern and are monitored for signs of leakage. These are:

1. Liquid Poison System (LPS)

2. Core Spray / Fire System (PIS)

3. Shutdown Cooling System (SCS)

The LPS contains five explosive squib valves (CV-4118, 19, 20, 21, 22) which isolate the RCS from the normally depressurized liquid poison tank..(See LPS drawing in Attachment 1). Although squib valves are inherently leak tight and cannot be routinely otroked, leakage to the LPS from the RCS is monitored by a ,

low range (0-100 psig) pressure gauge (PI-376) installed in the main control l room. This parameter is checked and recorded in the control room log once a shift and monitored during hourly readings. Any Reactor Coolant System pressure boundary leakage would cause a detectable pressure increase. l l

OC0587-0065-NLO2 070D2200D0 070515 i P,DR ADOCK 05000155 I '

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Nuclear' Regulatory Commission _ 2 Big Rock Point Plant Response to CL 87-06' May 15, 1987 The Core Spray System (PIS) has two independent trains which contain three isolation valves each. Each' train contains two motor operated gate valves

.(M0-7051,61/70,71) with a check valve (VPI-304/303) between them. (See PIS drawing in Attachment 1). Leakage to the PIS from the RCS is monitored by-

"tell-tale" lines installed between the check valve and the second motor operated valve in both core spray lines. Leakage from these "tell-tales" is monitored by auxiliary operators during bi-hourly rounds. Additionally, during monthly core spray valve operability tests, leakage from these "tell-tales" is checked to ensure proper valve closure.

i The Shutdown Cooling System (SCS) contains four pressure isolation valves.

(

I Both the inlet and outlet lines from the RCS to SCS contain two motor operated.

gate valves (MO-7058,59/56,57). (See SCS drawing in Attachment 1). Leakage l to the SCS during operation is monitored by pressure switches (PS-624/621) installed between the motor-operated isolation valves on the inlet and outlet lines. Any major leakage would cause a pressure switch actuation and a control room alarm. Any minor leakage from these lines is routed to the containment sump and would be detected.during the daily leak rate calculations for compliance to Technical Specification Reactor Coolant System pressure boundary leakage limits.

The only Technical Specification requirements associated with Reactor Coolant System pressure boundary leakage are the identified and unidentified leakage limits of 10 gpm and 1 gpm respectively, along with the requirement to perform this calculation daily while in power operation. Consumers Power Company

, feels that these requirements combined with the system design features as I discussed above are adequate to detect Reactor Coolant System pressure boundary leakage and initiate prompt mitigative actions if required.

l

. I h M /\

Ra1 2h R risch Senior Licensing Analyst

CC Administrator, Region III, NRC I NRC Resident Inspector - Big Rock Point Plant Accachment l

OC0587-0065-NLO2

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