IR 05000387/1985106
| ML17146A433 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/23/1986 |
| From: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Keiser H PENNSYLVANIA POWER & LIGHT CO. |
| Shared Package | |
| ML17146A434 | List: |
| References | |
| EA-86-106, NUDOCS 8607010113 | |
| Download: ML17146A433 (4) | |
Text
JUN 23 1986 Docket Nos.
50-387 50-388 EA-86-106 Pennsylvania Power
& Light Company ATTN:
Mr. H.
M. Keiser Vice President Nuclear Operations 2 North Ninth Street Al 1 entown, Pennsyl vania 18101 Gentlemen:
Subject:
NOTICE OF VIOLATION (Inspection Nos.
50-387/85-106; 50-388/85-04)
This refers to the NRC safety inspection conducted on March 15 - April 15, 1986, at the Susquehanna Steam Electric Station, Salem Township, Pennsylvania.
The inspection report was sent to you on May 7, 1986.
During the inspection, NRC inspectors reviewed the circumstances associated with a violation of a technical specification limiting condition for operation which was identified by your staff on April 10, 1986.
The violation involved the inoperability of two scram discharge volume (SDV) high water level transmitters for an entire operating cycle.
The transmitters provide input into the two Reactor Protec-tion System trip systems to shut down the reactor in the event of a high water level condition in the SDV.
On May 30, 1986, an enforcement conference was held with you and members of your staff to discuss the violation, its causes, and your corrective action.
The two transmitters were among four such transmitters installed in May 1985 as part of a modi fication performed in response to NRC IE Bulletin No. 80-17.
Two of the four transmitters were inoperable because isolation valves kept closed during the modification were not opened upon completion of the modifi-cation.
The NRC acknowledges that the safety significance of this violation was low because the other two transmitters were operable and provided redundant protection, as did four independent level float switches which had provided the only SDV high water level input to the Reactor Protection System prior to the modification.
However, the NRC is concerned that the valve checkoff list implemented upon completion of the modification erroneously indicated that the valves should be closed.
Further, although the post modification test verified that the transmitter itself was functioning, it did not verify that the transmitter would actually send a scram signal to the Reactor Protection System in the event of a high water level condition in the SDV.
This violation demonstrates the need for (1) increased attention to detail by personnel involved in the preparation and review of procedures and checklists used during the modification closeout process, and (2) improved testing of components after modifications to verify their ability to perform their intended safety func-tion.
8607010113 860623 PDR ADOCK 05000387
PDR OFFICIAL RECORD COPY i
CP SUSQUEHANNA 0001.0.0 06/20/86 X2L)l
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The violation is described in the enclosed Notice and has been classified at-Severity Level IV in accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
CFR 2, Appendix C (1985) (Enforce-ment Policy), based on its low safety significance.
Nonetheless, we emphasize that any similar violations in the future may result in additional enforcement action.
You are required to respond to the enclosed Notice and should follow the instructions specified therein when preparing your response.
Your written reply to this letter, especially as it relates to actions to prevent recurrence, and the results of future inspections will be considered in determining whether further enforcement action is appropriate.
In accordance with 10 CFR 2.790, a copy of this letter and its enclosure will be placed in the NRC Public Document Room.
The responses directed by this letter and the enclosed Notice are not subject to the clearance procedures of the Office of Management and Budget, otherwise required by the Paperwork Reduction Act of 1980, PL 96-511.
Sincerely, 0ri8in81 Signing py~
Richard W. Starostecki, Director Division of Reactor Projects Enclosure:
Notice of Violation cc w/encl:
A.
R. Sabol, Manager, Nuclear Quality Assurance M.
E. Barberich, Licensing Engineer T.
M. Crimmins, Superintendent of Plant-SSES A. J. Pietrofitta, General Manager, Power Production Engineering and Construction Atlantic Electric R. J.
Benich, Services Project Manager, General Electric Company B.
D. Kenyon, Senior Vice President-Nuclear Bryan A. Snapp, Esquire, Assistant Corporate Counsel William Matson, Allegheny Electric Cooperative Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector Commonwealth of Pennsylvania OFFICIAL RECORD COPY CP SUSQUEHANNA - 0004.0.0 06/20/86
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