ML20203B237
| ML20203B237 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/14/1986 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Muller D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.03, TASK-TM JPN-86-17, NUDOCS 8604180082 | |
| Download: ML20203B237 (4) | |
Text
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123 Main Street White Plains, New Wrk 10601 914 681.6240
- > NewYorkPbwer ett""r;;,.,
4# Authority
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April 14, 1986 JPN-86-17 Director of Nuclear Reactor Regulation U.
S.
Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Daniel R. Muller, Director BWR Project Directorate No. 2 Division of BWR Licensing
Subject:
James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 NUREG-0737 Item II.K.3.3 Safety / Relief Valve Failures and Challences
Reference:
1.
NYPA letter, C.
A. McNeill to D.
B. V.assallo, dated December 6, 1984 (.7 PN-8 4 - 8 0 ), "NUREG-0737 Proposed Changes to the Technical Specifications."
Dear Sir:
NUREG-0737 Item II.K.3.3 requires that failures and challenges to safety / relief valves (SRVs) be reported on an annual basis. to this letter provides a report of failures and challenges of SRVs as defined in Reference 1, occurring between I
January 1, 1985 and December 31, 1985 for the FitzPatrick Plant.
Should you or your staff have any questions regarding this l
matter, please contact Mr. J. A. Gray, Jr. of my staff.
Very truly yours, P
9%
ohn Brons Senior Vice Presiden't Nuclear Generation Enc.
cc:
Office of the Resident Inspector U.S. Nuclear Regulatory Commission P.O.
Box 136 Lycoming, New York 13093 1
8604180002 860414 ph p
ADOCK05000g3 DR I
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4 ATTACHMENT I TO JPN-86-17 SAFETY / RELIEF VALVE FAILURES AND CHALLENGES FOR 1985 1
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4 NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333
4 SAFETY / RELIEF VALVE FAILURES AND CHALLENGES DATE VALVE CHALLENGE FAILURE REMARKS 3/85 02-RV-71 C NO YES
- Valve Serial No. 1052 (Refuel Outage)
- Topworks of valve was removed during October 1984 maintenance outage due to suspected pilot valve leakage.
It was sent to Wyle Laboratories with the valves removed during the 1985 refueling outage.
Testing at Wyle Labora-tories showed a setpoint variance of +5.9% which exceeded the l
Technical Specifications allowable of 2 1%.
Valve was refurbished and certified at 1140 PSI
+1%.
I 3/85 02-RV-71 E NO YES
- Valve Serial No. 1050 l
(Refuel Outage)
- Topworks of valve was removed during October 1984 maintenance i
outage due to suspected pilot valve l
leakage.
It was sent to Wyle l
Laboratories with the valves removed during the 1985 refuel l
outage.
Testing at Wyle showed a setpoint variance of +2.3% which a
exceeded the Technical Specifi-cations allowable of 1%.
Valve was refurbished and certified at 1105 PSI 1%.
3/85 02-RV-71 A NO YES
- Valve Serial No. 1045 (Refuel Outage)
- Recertification at Wyle showed a l
setpoint variance of +6.1% which j
exceeds the Technical Specifi-cations allowable of 1%.
Valve was refurbished and certified at 1140 PSI +1%.
l l
i L
DATE VALVE CHALLENGE FAILURE REMARKS e
3/85 02-RV-71 E NO YES
- Valve Serial No. 1056 (Refuel Outage)
- Recertification at Nyle showed a setpoint variance of +2.7% which exceeds the Technical Specifi-cations allowable of 1%.
Valve was refurbished and certified at 1105 PSI 1%.
3/85.
02-RV-71 H NO YES
- Valve Sarial No. 1051 (Refuel Outage)
- Recertification at Wyle showed'a setpoint variance of +6.2% which exceeds the. Technical Specifi-cations allowable of 1 %.
Valve 1
was refurbished and certified at 1090 PSI 1%.
7/19/85*
O2-RV-71 A YES(Note 1)
NO
- Valve Serial No. 1045 02-RV-71 D YES(Note 1)
NO
- Valve Serial No. 1080 l
02-RV-71 F YES(Note 1)
NO
- Valve Serial No. 1097 02-RV-71 G YES(Note 2)
NO
- Valve Serial No. 1012 02-RV-71 H YES(Note 1)
NO
- Valve Serial No. 1087 l
02-RV-71 J YES(Note 1)
NO
- Valve Serial No. 1110 02-RV-71 K YES(Note 1)
NO
- Valve Serial No. 1047 L
02-RV-71 L YES(Note 1)
NO
- Valve Serial No. 1062 l
10/31/85 02-RV-71 K YES(Note 1)
NO
- Valve Serial No.
1047 l
l l
NOTE:
1 - Challenge caused by system pressure i
2 - Challenge caused by operator demand At the next scheduled refueling outage, the topworks of 02-RV-71 E will be removed and tested to verify its performance during this transient.
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