ML20008G102
| ML20008G102 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/29/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-08-02, TASK-8-2, TASK-RR NUDOCS 8107020248 | |
| Download: ML20008G102 (5) | |
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Docket No. 50-219 LS05-81-06-il 6 v f gf, y
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Dear Mr. Finfrock:
SUBJECT:
SEP TOPIC VIII-2, ONSITE EMERGENCY POWER SYSTEMS - DIESEL GENERATOR SAFETY EVALUATION FOR OYSTER CREEK i
l The enclosed staff safety evaluation is based on contractor's documents that have been made available to you previously. These documents support l
the findings of the staff safety evaluation of Topic VIII-2 that recomends l
modifications to the diesel generator *rotective interlocks.
The need to actually impl'ement these changes will be detennined during the integrated safety assessment. This topic assessment pay be revised in-the future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessment is completed.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing i
Enclosure:
As stated cc w/ enclosure:
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June 29, 1981
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Docket No. 50-219 LS05-81-06-116 Mr. I. R. Finfrock, Jr.
Vice President - Jersey Central Power & Light Company Post Office Box 388 Forked !!iver, New Jersey 08731
Dear Mr. Finfrock:
SUBJECT:
SEP TOPIC VIII-2, ONSITE EMERGENCY POWER SYSTEMS - DIESEL GENERATOR, SAFETY EVALUATION FOR OYSTER CREEK The enclosed staff safety e.aluation is based on contractor's documents that have been made available to you previously. These documents support the findings of the staff safety evaluation of Topic VIII-2 that reconsnends modifications to the diesel generator protective inter 10cks.
The need to actually implement these changes will be determined during the integrated safety assessment. This tc71c assessment may be revised 11 the future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessment is completed.
. Sincerely, 7M. OudL/d Dennis M. Crutchfield, ChAf Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page 5 *,.
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Mr. I. R. Fi nf rock, J r.
CC G. F. Trowbridge, Esquire Gene Fisher Shaw, Pittman, Potts and Trowbridge Bureau Chief 1800 M Street, N. W.
Bureau of Radiation Protection Washington, D. C.
20036 380 Scotts Road Trenton, New Jersey 08626 J. B. Lieberman, Esquire Beriack, Israels & Lieberman Commissioner 26 Broadway New Jersey Department of Energy New York, New York 10004 101 Commerce Street Newark, New Jersey 07102 Natural Resources Defense Council 91715th Street, N. - W.
Licensing Supervisor
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Washington, D. C.
20006 Oyster Creek Nuclear Generating Station J. Knabel P. O. Box 388 BWR Licensing Manager Forked River, New Jersey 08731 Jersey Central Power &, Light Cogany Madison Avenue at Punch Bowl Road Resident Inspector Morristown, New Jersey 07960 c/o U. S. NRC P. O. Box 445 Joseph W. Ferraro, Jr., Esquire Forked River, New Jersey 08731 l
Deputy Attorney General State of New Jersey Department of Law and Public Safety l
1100 Raymond Boulevard l
Newark, New Jersey 07012
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l Ocean County Library Brick Township Branch 401 Chambers Bridge Road j
l Brick Town, New Jersey 08723 l
Mayor Lacey Township P. O. Box 475 Forked River, New Jersey 08731 Commissioner Department of Public Utilities State of New Jersey 101 Connerce Street Newark, New Jersey 07102 U. S. Environmental Protection l
. Agency Region II Office ATTN: EIS COORDINATOR 26 Federal Plaza New Yo:t, New York 10007 i
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TCPIC: VIII-2, ONSITE EMLRGENCY POWER SYSTEMS - DIESEL GENERATOR I.
Introduction' Diesel generators, which provide emergency standby power for safe reactor
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shutdown in the event of total loss of offsite power, have experienced a significant number of failures. The failures to date have been attributed to a variety of causes, including failure of the air startup, fuel oil, and combustion air systems.
In some instances, the malfunctions were due, to lockout. The information available to the control room operator to indicate the operational status of the diesel generator was imprecise and could lead to misinterpretation. This was caused by the sharing of a single annunciator station by alarms that indicate conditions that render a diesel generator unable te respond to an automatic emergency start signal and alarms that only india ;e a warning of abnormal, but no disabling, conditions. Another cause was the wording on an annunciator window which did not specifically say that the diesel generator was inoperable (i.e.,
" unable at the time to respond to an automatic emergency start signal) when in fact it was inoperable for that purp,ose. The review included the reliability, protective interlocks, fuel oit quality, and testing of diesel generators to assure that the diesel generator meets tha avail-ability requirements for providing emergency standby power to the engineered safety features.
II.
Review Criteria The review criteria are presented for Section 8.3.1 in Table 8-1 of the Standard Review Plan.
III. Related Safety Topics and Interfaces The scope of review for this topic was limited to avoid duplication of effort since some,0spects of the review were performed under related topics. Related topics and the subject matter are identified below.
Each of the related topic reports contain the acceptance criteria and review guidance for its subject matter.
III-12 Environmental Qualification VI-7.C.1 Independence of Onsite Power VIII-1.A Degraded Grid XVII Fuel Oil Quality Assurance 1
There are no safety topics that are dependent in the present topic informa-tion for their completion.
g IV.
Review Guidelines The review guidelinas are presented in Section 8.3.1 of the Standard Review Plan.
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Evaluation -
The concern with regard to annunciators was pursued as a generic issue.
The staff safety evaluation for Oyster Creek concluded that in order to provide the operator with accurate, complete and timely information pertinent to the status of the diesel generators, as required by IEEE Std 279-1971, the following corrective actior.s are required:
- 1) Clearly distinguish between both disabling and nondisabling con-ditions that are shared on one single "D/G TROUBLE" annunciator.
- 2) Provide information sufficient to determine if the D/G is provided with a manual shutdown lockout relay.
By a letter dated May 17, 1978, the licensee agreed to make suitable modifications to the annunciators.
Also, as a result of the work done by the University of Dayton, a generic program for implementing most of the recommendations for re-liability enhancement that are contained in the University of Dayton report is being conducted by NRC. This latter program will also determine the adequacy of the diesel generator testing program on a case-by-case basis and enforce any necessary changes.
.The question of fuel oil quality was addressed on a generic basis in January 1980, by letters to all licensees. The letters required that licensees include fuel oil in their Quality Assurance program. The Quality Assurance program is addressed in Topic XVII. Until completion of Topic XVII, the periodic testing of the diesels is considered to be an adequate interim method for assuring acceptable quality in the fuel oil stored on site.
l Beyond these efforts, EG&G Report 0713F, " Diesel Generators" presents a technical evaluation of the diesel generator protective interlocks and load capability at Oyster Creek against present licensing criteria. The report notes that five diesel-generator protective trips are not bypassed during emergency operation. This is not in agreement with current NRC guidelines that specify that only engine overspeed and generator differential may be used during emergency operation.
VI.
Conclusion l
The staff proposes that the diesel generator protective interlocks be <
l brought into conformance with the Branch Technical Position ICSB-17 (PSB).
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