ML20210D838
| ML20210D838 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/11/1986 |
| From: | Gallo R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| Shared Package | |
| ML20210D845 | List: |
| References | |
| NUDOCS 8609220018 | |
| Download: ML20210D838 (2) | |
See also: IR 05000352/1986017
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SEP 111986
Docket No. 50-352
Philadelphia Electric Company
ATTN: Mr. S. L. Daltroff
.Vice President
Electric Production
2301 Market Street
Philadelphia, PA
19101
Gentlemen:
Subject:
Inspection 50-352/86-17
~This transmits the findings of a special safety inspection by Mr. E. M. Kelly
on July 21 - 31, 1986, at Limerick Generating Station, Limerick, Pennsylvania.
The inspection consisted of a~ review of the causes for a problem identified by-
a_ licensed operator on July 18 wherein two non-automatic primary containment-
isolation valves in the drywell chilled water system were found to be .
incapable of remote manual _ isolation from the control room for 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br />. The
findings were based on interviews, observations and a review of the design of
the isolation valves, and are described in the NRC_ Region I Inspection Report
which is enclosed with this letter. The findings were also discussed at
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meetings held on July 25 and August 1,- 1986 with Mr. J. F. Franz, Jr. and
J. Doering of your staff.
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As a result of this inspection, we determined that the Technical Specification
for containment isolation valves was not met during the time that the valve
motors were de-energized. Although the error affected outboard isolation
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valves in two separate drywell penetrations whose inboard isolation valves are
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automatic and were operable, we are concerned that these valves were not
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recognized by licensed operators as essential for primary containment
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isolation. And, even though these valves are the subject of Limerick License
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Condition 2.C.10 as a schedular exemption from 10CFR50, Appendix A, General
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Design Criterion 56 during the first fuel cycle of Limerick Unit 1 operation,
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we determined that not only were operators generally unaware of the License
Condition but also'that the valves are not currently capable of remote manual
isolation from the control room. .Further, previous problems associated with
operator knowledge and control of containment isolation valves have been.
experienced at Limerick that were not effectively addressed by licensed
operator requalification training. This weakness has persisted despite a
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number of corrective actions implemented by your staff.
-We are concerned about the apparent weakness in training afforded licensed
operators regarding the requirements and recognition of primary containment
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isolation valves and, accordingly, to emphasize this concern, a violation of
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NRC~ requirements is cited in Appendix A.
A reply is required and sFould be
860922001886091y
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Philadelphia Electric Company
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prepared in accordance with Appendix A.
Additionally, a deviation from a
commitment made in the Final Safety Analysis Report in support of License
Condition 2.C.10 is identified in Appendix B.
A reply to the Deviation is also
requested. Your replies to Appendices A and B are exempt from the Office of
Management and Budget clearance procedures under the Paperwork Reduction Act of
1980, PL 96-511.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosures
will be placed in the Public Document Room. Your cooperation is appreciated.
Sincerely,
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Original Signed Byt
Robert M. Gallo, Chief
Projects Branch No. 2
Division of Reactor Projects
Enclosures:
1.
NRC Region I Inspection Report 50-352/86-17
2.
Appendix A, Notice of Violation
3.
Appendix B, Notice of Deviation
cc w/encls:
V. S. Boyer, Senior Vice President, Nuclear Power
John S. Kemper, Vice President, Engineering and Research
J. Franz, Manager, Limerick Generating Station
Troy B. Conner, Jr. , Esquire
Eugene J. Bradley, Esquire, Assistant General Counsel
W. M. Alden, Engineer in Charge, Licensing Section
Public Document Room (PDR)
local Public Document Room (LPDR)
Nuclear Safety Info iation Center (NSIC)
NRC Resident Inspector
Commonwealth of Pennsylvania
bec w/encls:
Region I Docket Room (with concurrences)
Management Assistant, ORMA (w/o encl)
Section Chief, DRP
SRI, Peach Bottom Atomic Power Station
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