JPN-87-034, Forwards List of Pressure Isolation Valves in Plant & Description of Periodic Leakage Tests Performed on Valves in Response to Generic Ltr 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves
| ML20215C801 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/11/1987 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-87-06, GL-87-6, JPN-87-034, JPN-87-34, NUDOCS 8706180251 | |
| Download: ML20215C801 (3) | |
Text
E q
7 123 Main Strem WNto Rairm, New bek l0601 -
914 681.62 %
]
.i
- > NewYorkPbwer 1
l 4# Authority i
l June 11, 1987.
E JPN-87-034 i
U.
S.
Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C..
20555
Subject:
James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 Response to Generic Letter 87-06 --- Periodic 1
Verification of Leak Tight Integrity of Pressure Isolation Valves kl
Reference:
- 1. Generic Letter 87-06, " Periodic verification of leak tight integrity of pressure isolation l
valves", dated March 13, 1987.
Dear Sir:
Generic Letter 87-06 (Reference 1) r6 quested a list'of the pressure isolation valves in the FitzPatrick plant, and a description of any periodic leakage tcsts which are performed on the valves.
This information is provided in' Attachment 1 to this letter.
The Attachment also shows that all of the prensure isolation valves require leakage testing in accordance with the FitzPatrick Technical Specifications.
Should you or your staff have any questions regarding this matter, please contact Mr.
J.
A.
Gray, Jr. of my staff.
Very truly yours,
.q
).
I L
\\
olt Brons.
j Exe ive Vice President Nuclear Generation
)
cc: (list on next page) 1 l
I i
8706180251 870611 1
PDR ADOCK 05000333 4
ho P
PDR gO
/
- 1/ t.
y i'>
l It l
(
l' 1
)
s cc:
Of fi'ce of the Resident Inspector j
U.
S.
Nuclear Regulatory Commission i
P.
0.
Box 136 j
Lycoming, New York 13093 q
)
U.
S.
Nuclear Regulatory Commission Region I 631 Park Avenue z
King of Prussia, PA 19406 9
Mr. Harvey Abelson Project Directorate I-1 Division of Reactor Projects-I/II U.S.
Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 1
i l
i i
I I
i I
1
-l
.Q" ATTACHMENT I TO.JPN-87-34 NEW YORK POWER AUTHORITY.
JAMES A.
FITZPATRICK. NUCLEAR. POWER PLANT PRESSURE ISOLATION' VALVES i
l System:
Leak-Rate Acceptance Criteria LLRT Pressure Test l
Valve No.
Description
-(45 psig-air) (1000 psig water) 10'AOV-68A,B LPCI Injection Testable Check 11 scfm or 10 gpm Valve (2)
(@45 psig)
(@l000 psig)
MOV-17 Outboard Shut Down Cooling 200 scfd Suction Isolation Valve-MOV-18 Inboard Shut Down Cooling 150 scfd Suction Isolation Valve MOV-25A,B LPCI Inboard Injection 300-scfd Isolation Valve (2)
MOV-32 Inboard Head Spray Isolation 30 scfd Valve MOV-33 Outboard Head Spray Isolation 30 scfd Valve System:
Core Spray (CS)
Leak Rate Acceptance Criteria LLRT Pressure Test Valve No.
Description (45 psig air) (1000 psig water) 14 MOV-12A,B Inboard Injection Isolation 75 scfd Valve (2)
AOV-13A,B Injection Testable Check 11 scfm or 10 gpm Valve (2)
(@45 psig)
(@l000-psig)
All valves are normally closed and all tests. are conducted once each operating cycle in accordance with Appendix J, Type B test requirements (except for cyclic pressure test on valves 10 AOV-68A,B and 14 AOV-13 A,B),
i as specified in the Technical Specifications.
,