ML20235G388
| ML20235G388 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 06/24/1987 |
| From: | Selman M CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-87-06, GL-87-6, NUDOCS 8707140238 | |
| Download: ML20235G388 (5) | |
Text
i Murr:y Selmin Vee Prssident i
Consolidated Edison Company of New York, Inc.
Indian Point Station Broadway & Bleakley Avenue Buchanan, NY 10511 Telephone (914) 737-8116 June 24, 1987 Re:
Indian Point Unit No. 2 Docket No. 50-247 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Response to Generic Letter 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves Dear Eirst This is in response to your letter dated March 13, 1987 (Generic Letter 87-06) regarding reactor coolant system (RCS) pressure isolation valves and the measures in place to assure the leak-tight integrity of the valves.
Pressure isolation valves (PIVs) are defined for each interface as any two valves in series within the RCS pressure boundary which separate the high pressure reactor coolant system from an attached lower pressure system.
These valves are normally closed during power operation.
The generic letter requested a list of all PIVs and a description of the periodic tests or other measures performed to assure the leak-tight integ-rity of the valves along with the acceptance criteria for leakage and frequency of testing.
Accordingly, Attachment A to this letter provides our response to Generic Letter 87-06.
Should you or your staff have any additional questions, please contact us.
Very truly yours, 22.190.6.19.1 Attachment ec:
Mr. William Russell Regional Administrator - Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 8707140238 870624 10 l
PDR ADOCK 05000247 P
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PDR t
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Ms. Marylee M. Slosson-
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Project Manager j
Project Directorate I-1 Division of' Reactor Projects I-II U.S. Nuclear Regulatory Commission-1 Washington, DC 20555 i
Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 38 Buchanan, NY 10511 i
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ATTACHMENT A Indian Point Unit No. 2 Response to Generic Letter 87-06
" Periodic Verification of Pressure Isolation Valves" I. PIVs Subject to Inservice Testing (IST) Program Most of the PIVs at Indian Point Unit No. 2 (IP2) are tested in accordance with the requirements of the IP2 Inservice Testing Program.
The remaining are tested by Technical Specification requirements.
Included in this category are valves forming the pressure boundary between the higher reactor coolant system and the lower residual heat removal and safety injection systems.
Valves Function Testing Frequency MOV730 Pressure isolation motor operated Leak Rate Refueling MOV731 valves between RCS and RHR System and from the hot leg of RCS loop 2 Full-Stroke Cold Shutdown to RHR pump suction exercised 857 A,B,C,D Pressure isolation check valves Leak Rate Refueling 857 F,G,H,M in the High Pressure Safety and Injection (HPSI) lines to the Full-Stroke Refueling RCS hot legs exercised 857 J,K Pressure isolation check valves Leak Rate Refueling in the High Pressure Safety and Injection (HPSI) lines to the Full-Stroke Refueling RCS cold legs (loop 21 and exercised loop 23) 895 A,B,C,D Pressure isolation check valves Leak Rate Refueling in the outlet lines from the and accumulators to the RCS cold legs Full-Stroke Refueling exercised II.
PIVs Testing Required By Technical Specifications Valves Function Testing Frequency 897 A,B,C,D Pressure isolation check valves Leak rate Cold shutdown, in the SIS cold leg injection Refueling lines to the RCS to permit flow and after from the SIS into the RCS maintenance, following a LOCA.
repair or replacement Full-Stroke Cold Shutdown exercised and Refueling 838 A,B,C,D Pressure isolation check valves in Leak Rate Cold Shutdown, the RCS cold leg injection lines Refueling and from the recirculation pumps and after mainten-RHR pumps to permit flow from these ance, repair or pumps in the Low Pressure SI mode replacement following a LOCA.
Full-Stroke Refueling exercised III. PIV's Leakage Measured by other methods Valves Function Testing 508 A,B RCS loop drain valves to Daily water inventory balance 505 A,B the waste disposal system of Reactor Coolant System 511 A,B inventory and leakage into 515 A,B closed systems quantifies leakage past the loop drain valves.
Technical Specifications lLmit identified RCS leakage to 10 gpm i
I during power operation. Thus, these operating restrictions serve in lieu of direct leak rate tests for these valves.
HCV 123 Excess letdown path for Daily water inventory 213 RCS to CVCS Volume Control balance of Reactor Coolant Tank System inventory and leakage into closed systems quantifies any leakage past the the excess letdown valves. Technical Specifications limit identified RCS leakage to 10 gpm during power operation. Thus, these operating restrictions serve in lieu of direct leak rate tests for j
these valves.
=_. _ _ _ _.
Note. (1)
Leak rate test acceptance criteria are within limits of IP2 Technical Specification 3.1.F.2.b.
Each pressure isolation valve 'shall satisfy the followings (a)
Leakage rates less than or equal to 1.0 gpm are acceptable.
(b) Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are acceptable If the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between the measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.
(c)
Leakage rate greater than 5.0 gpm are unacceptable.
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