JAFP-81-0258, Responds to IE Bulletin 80-25, Operating Problems W/Target Rock Safety-Relief Valves at Bwrs. During 1980 Refueling Outage Installation of 2-stage Target Rock Safety Relief Valves Completed & Solenoid Operated Valves Replaced
| ML19350C480 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/19/1981 |
| From: | Pasternak R POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-80-25, JAFP-81-0258, JAFP-81-258, NUDOCS 8104030288 | |
| Download: ML19350C480 (3) | |
Text
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- D, POWER AUTHORITY OF THE STATE OF NEW YORK J AMES A. FITZPATRICK NUCLEAR POWER PLANT S
RAYMOND J. PAsTERNAK P.O. Box 41 ResWeat Man ger Lycommg, New York 13093 315-342 3840 SERI AL:
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Boyce H. Grier, Director g
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SUBJECT:
NRC I&E BULLETIN 80 OPERATING PROBLEMS WITH ROCK SAFETY - RELIEF VALVES AT BWRs
Dear Mr. Grier:
The FitzPatrick Plant staff has completed a review of the subject bulletin and provides below our response.
During the 1980 Refueling and Maintenance Outage, installation of two-stage Target Rock Safety Relief Valves (SRV) was completed.
This installation completed the phase-out of three-stage valves which began with the installation of two (2) two-stage valves during the 1978 Refuel Outage, seven (7) two-stage valves during the 1979 Regulatory Outage for pipe stress considerations and the remaining two (2) two-stage valves during 1980 as noted above.
In addition to completing the installation of two-stage SRVs during the 1980 Refueling Outage, the solenoid operated valves which actuate the SRVs upon operator demand and/or in the Automatic Depressurization Mode, were also replaced. The original installation solenoid operated elve was of a single solenoid design in Safety Division I.
These solenoid operated valves were replaced by an assembly containing both Division I and II solenoid operated valves to allow manual (operator demand) operation of SRVs utilizing the Division II solenoid if required as the result of a severe fire in certain plant areas.
With respect to attempts to operate the two-stage SRVs in their present configuration, each valve was test operated at approximately 250 psig in early ~ August 1980 as part of the post refuel-startup test program. This test utilized only the Division I solenoid as portions of the Division II control circuits were not yet completed.
No failures or problems were encountered.
In mid-October 1980, following a reactor scram M D 4 0 3 O *bS b %
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Boyce H. Grier, Director March 19, 1981 United States Nuclear Regulatory Comniission JAFP 81-0258
SUBJECT:
NRC I&E BULLETIN 80-25 Page and isolation, SRVs functioned normally in the pressure demand mode and no problems were evident in response to operator demand for valve operation.
Plant records indicate that SRV G and H were operated once each to centrol pressure.
On January 17, 1981, following a reactor scram and isolation, SRVs again functioned normally in the pressure demanJ mode.
However, an attempt to operate SRV "G" did no. result in opening of the valve. SRV K, H, A and B were operated once each for pressure control and the response to operator demand was normal.
During the maintenance outage following the January 17, 1981 shutdown, investigation into cause of the earlier SRV G failure revealed the presence of excess adhesive in the solenoid valve. This find'ng was reported in Licensee Event Report 81-001. Each of the eleven (11) solenoid operated valve assemblies was disassembled, cleaned, reassembled, bench tested and reinstalled under the technical direction of a vendor representative.
Following installation on the SRV, several solenoid valve initially appeared to be malfunctioning.
Investigation revealed air (nitrogen) leaks due to failure of 0-rings to properly seat,(or energize) as a result of inadequate lubrication of the 0-rings.
Subsequent tests of the eleven solenoid valve assemblies (using both Division I and II solenoids) were satisfactory.
In addition, test of each SRV at approximately 250 psig during the subsequent plant startup was satisfactory.
With respect to paragraph 2 of the Bulletin, Maintenance Procedures associated with SRV replacement and maintenance, have been revised to reflect the content of the paragraph.
A review of the SRV pneumatic supply system has been conducted.
i This review indicates that the maximum pressure available to the solenoid valves could be as high as 200 psig. This pressure could be reached only as a result of several failures in the nitrogen supply system. General Electric Company Service Information Letter 196, Supplement 8, indicates that the maximum pressure capability of the solenoid valves is 135 psig. Modification of the pneumatic supply at a point just prior to the air (nitrogen) line penetrating primary containment is planned.
This modification (which is in the conceptual design stage) would provide additional over pressure protection and provide nigh and low air (nitrogen) pressure alarms.
Implementation of Annunciator Response Procedures and completion of the modifications (depending on material availability) is expected during the Fall 1981 Refueling and Maintenance Outage.
Very truly yours,
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~RJP:VC:brp RAYMOND J. PASTERNAK RESIDENT MANAGER Subscribed and Sworn to before me this 19th day of March,1981 m
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BEVERLY R.PRUcNAL. fis 349, Notary Pub ic Notary PudG:- ctate of !!ew Ycrk Ap;;:nte: fin cm: soc unty o3 MyCem:ris:
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6 Boyca 11. Grier, Director March 19, 1981 United States Nuclear Regulatory Commission JAFP 81-0258
SUBJECT:
NRC I&E BULLETIN 80-25 Page DISTRIBUTION:
George T. Berry, PASNY, NY0 J. P. Bayne, PASNY, NY0 A. Klausmann, PASNY, NY0 J. F. Davis, PASNY, NY0 C. M. Pratt, PASNY, NY0 G. M. Wilverding,-PASNY, NY0 R. Baker, PASNY, JAF M. C. Cosgrove, PASNY, JAF R. J. Converse, PASNY, JAF M. N. Brosee, PASNY, JAF H. N. Keith, PASNY, JAF W. Fernandez, PASNY, JAF D. E. Tall, PASNY, JAF NRC Resident Inspector NRCB 80-25 File Document Control Center 4
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