ML20215E795
| ML20215E795 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/11/1987 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-87-06, GL-87-6, NUDOCS 8706220113 | |
| Download: ML20215E795 (6) | |
Text
Northern States Power Company 414 Nicollet Mall Minneapoks. Minnesota 55401 Telephone (612) 330 5500
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June 11,1987 Generic Letter 87-06 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Resoonse to Generic Letter 87-06 Generic Letter 87-06, " Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves", requested a list of all pressure isolation valves at Prairie Island.
For each valve listed, the generic letter also requested a description of the periodic tests or other measures performed to assure the integrity of the valve as an independent barrier at the reac-tor coolant pressure boundary along with the acceptance criteria for leak-age, operational limits, and frequency of test performance.
The attached information is provided in response to that request.
Please contact us if you have any questions related to the information we have provided.
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David Musolf Manager - Nuclear Support Services DMM/EFE/jlk c: Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC G Charnoff Attachment 8706220113 870611 CV0 1
PDR ADOCK 05000282 P
June 11, 1987 Page 1 of 5 Response to Generic Letter 87-06 UNIT 1 VALVE NUMBER AND NAME MEASURES TO ASSURE INTEGRITY AND ACCEPTANCE CRITERIA FOR LEAKAGE SI-9-3 Low - Pressure SI to See Note 1 SI-9-4 Upper Plenum SI-9-5 SI-9-6 SI-6-2 RHR to Loop B See Note 1 Accumulator Inj Lin 32164 RHR Suct From.
See Note 2 32165 Reactor Coolant System 1
32230 32231 32066 RHR Return to See Note 2 Reactor Coolant System SI-6-1 Accumulator Outlet See Note 2 SI-6-3 Check Valves SI-6-4 RC-10-1 Pressurizer Code See Note 3 RC-10-2 Safety Valves 32195 Pressurizer PORV See Note 4 32196 Isolation valves 31231 Pressurizer PORV See Note 4 31232 32400 RCS Sample See Note 2 32401 Valves 32402 32403 32404 32405 j
June 11, 1987 Page 2 of 5 UNIT 1 VALVE NUMBER AND NAME MEASURES TO ASSURE INTEGRITY AND ACCEPTANCE CRITERIA FOR LEAKAGE RC-1-1 RCS Loop Drain See Note 5 RC-1-2 Manual Valves RC-1-3 RC-1-4 37035 Reactor Vessel See Note 6 37036 Head Vent Valves 37037 37038 37039 31447 Accumulator Leak Rate Test See Note 2 31449 Control Valve e
4 UNIT 2 2SI-9-3 Low-Pressure SI to See Note 1 2SI-9-4 Upper Plenum 2SI-9-5 2SI-9-6 2SI-6 2 RHR to Loop B See Note 1 Accumulator Inj Lin
\\
32192 RHR Suct from See Note 2 32193 Reactor Coolant System 32232 32233 i
32169 RHR Return to See Note 2 Reactor Coolant System i
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P June 11, 1987 Page 3 of 5 UNIT 2 VALVE NUMBER AND NAME MEASURES TO ASSURE INTEGRITY AND ACCEPTANCE CRITERIA FOR' LEAKAGE 2RC-1-1 RCS Loop Drain-See Note 5 2RC-1-2 Manual Valves 2RC-1-3 2RC-1-4 37091 Reactor Vessel See Note 6 37092 Head Vent Valves 37093 37094 37095 31459 Accumulator Leak Rate See Note 2 31461 Test Control Valve
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i 2SI-6-1 Accumulator Outlet See Note 2
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2SI-6-3 Check Valves 2SI-6-4 2RC-10-1 Pressurizer Code See Note 3 2RC-10-2 Safety Valves 32197 Pressurizer PORV See Note 4 32198 Isolation Valves 31233 Pressurizer PORV See Note 4 31234 32406 RCS Sample See Note 2 32407 Valves 32408 32409 32410 32411 a
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June 11, 1987 Page 4 of 5 NOTE 1:
This is an " Event V Order" Valve.
Leak Rate Testing is required by current Plant Technical Specifications I
(T.S.).
Acceptance criteria for leakage are stated in T.S.4.3.
NOTE 2:
This is a category "A"
Valve.
Leak Rate Testing is done in accordance with the ASME Section XI Code and the Prairie Island Inservice Testing Program.
(
Acceptance criterion for leakage is less than one l
gallon per minute.
l l
l NOTE 3:
This is a category "C" valve.
The Safety Valve is
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tested on a five-year interval in accordance with ASME Section XI Code and the Prairie Island Inservice Testing Program.
Each safety valve has an individual outlet temperature sensor to detect leakage.
An acoustic sensor common to both safety valves also detects valve leakage.
Current TS have operability requirements for the sensors.
Acceptance criteria for leakage are stated in T.S.3.1.C.
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NOTE 4:
Each valve has an acoustic sensor and a valve position r
There is one common temperature sensor to monitor leakage of the four valves.
Current plant T.S.
includes operability requirements for the sensors.
Acceptance criteria for leakage are stated in T.S.3.1.C.
NOTE 5:
Any leakage past these valves changes the inventory in l
the reactor coolant drain tank.
This inventory is monitored daily.
Acceptance criteria for leakage are stated in T.S.3.1.C.
NOTE 6:
This is a category "B" valve.
The operability of this valve is verified in accordance with the ASME Section XI Code and the Prairie Island Inservice Testing Program.
Acceptance criteria for leakage are stated in T.S.3.1.C.
a i
e June 11, 1987 Page 5 of 5 NOTE 7:
Leakage from vent and drain valves off the reactor coolant system is monitored by:
a)
Monthly containment inspection, b)
Daily leakage test of the reactor coolant system.
This "On Line" leak test measures all sources of reactor coolant leakage including leakage past pressure isolation valves into low pressure systems.
c)
Containment radiation monitors.
Acceptance criteria for leakage are stated in T.S.3.1.C.
Isolation valves in the charging and letdown system, reactor l
coolant pump seal injection, and high head safety injection are not considered pressure isolation valves.
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