ML19341C682
| ML19341C682 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/24/1980 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| LSO5-80-11-037, LSO5-80-11-37, NUDOCS 8103030970 | |
| Download: ML19341C682 (4) | |
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UNITED STATES i
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'lo ve-te r 24, 1900 Occk et No. 50-219
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TO ALL POWER REACTOR LICENSEES WITH PLANTS A
LICENSED PRIOR TO JANUARY 1,1979
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The Comission published on November 19, 1980 (45 FR 76602),., C. c Section 10 CFR 50.38 ano a new Appendix R to 10 CFR 50 regarding fire pectection features of nuclear pcwer plants. The revised Section 50.38 and Appendix R will meccme effective February 17, 1981, which is 90 days after publication.
A ccpy of the Federal Rec 1 ster Notice is enclosed (Enclosure 1).
The provisions of Ascendix R that are applicable to the fire protection features of ycur f acility can be divided into two categories. The first categcry consists of :ncse provision of the A:pendix that are required to be backfit in their entirety by the new rJle, regardless of whether or not alternatives to the specific requirements of these Sections have been previously a0 proved by the NRC staff. These recuirements are set forth in Sections III.G. Fire Protection of Safe Shutdown Capability; III-J.
Emergency Lighting; and III-0, Oil Collection Systems for Reactor Ccolant Pump.
The fire protection features of your f acility must satisfy the specific recuirements of these three Sections by the dates established by Paragrapn 50.48(c), unless an exemetion frem the Appendix R requirements is approved by the Ccmissicn.
You shculd note the provisions for tolling the time for cormleting the modifications required by these three Sections of Appendix R set forth in Paragraph 50.48(c)(6).
i The second categcry of Accendix R provisions applicable to the fire protection features of ycur f acility consists of requirements concerning the "open' items of previous NRC staff fire protection reviews of your f acility. An open item is defined as a fire protection feature that has not been previously approved by the NRC staff as satisfying the provisions of Appendix A to Brancn Technical Position BTP PCSB 9.5-1, as reflected in a staff fire protection safety evaluation report. The fire protection features of your f acility that are in this category must satisfy the specific recuirements of Appendix R by tne dates established by Paragraph 50.48(c), unless an exem -
tion fecm the A:pendix R requirements en those features is accroved by tne Comi s sion. is a summary listing of the caen items concerning the fire protecticn features of your f acility based on a review of our records. Also included is cur :csnien on the saecific recuirements that mst be satisfied in order to resolve these open items.
If ycu have any cuestions or disagree-ments witn this enclosure, clease advise us witnin 30 days of your receipt of tnis !etter.
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2 Witn regard to the fire protection modifications that nave ceen previcusly approved oy the NRC staff, Paragraoh 50.48(c) specif f es a new senedule for their concletion.
This paragraph, whea it oecomes effective, will supersede the currently affective section of the regulations tnat temocrarily suspencs completion dates for previcusly approved fire protection modifications tnat are given in f acility license conditions (45 FR 71569, Octooer 29,1980).
The Commission expects that all such modifications will be completed in accordance with this new schedule, unless an extension has been requested and granted by the Director of the Office of Nuclear Reactor Regulation i
[see Paragraon 50.48(d)], or an exemotion has been recuested and grantec by
.he Cocmission pursuant to Section 50.12 of the Connission's regulations.
i If you have creviously recuested extensions of dates for comoletion of modifications that are required by license conditions for your facility whicn were not accroved, and you have determined that nese extensions are still necessary and justifiaole, it will be necessary for you to reapply for any such extensions in accordance with the provisions of Paragrapn 50.43(d).
All requests for Commission action resulting from this rule are subject to the senedule of fees specified in 10 CFR 170.21.
If you nave any questions concerning the subject matters of this letter, clease contsc the NRC Project Manager for your facility.
Sincerely,
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-W&MMby-C GS 7
Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Re921ation
Enclosures:
1.
Notice - Fire Protecticn Rule 2.
Summary of Staff Require-i ments to Resolve Ocen
! tems cc w/ enclosures:
See next page 1
Mr. I. R. Finf rock, J r. November 24, 1980 cc w/ enclosures:
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 08628 GPU Service Corporation ATTN: Mr. E. G. Wallace Comissioner Licensing Manager New Jersey Depart:nent of Energy 260 Cherry Hill Road 101 Conterce Street Parsippany, New Jersey 07054 Newark, New Jersey 07102 Natural Resources Defense Council Plant Superintendent 91715th Street N. W.
Oyster Creek Nuclear Generating Washingten, D. C.
20006 Station P. O. Box 388 Forked River, New Jersey 08731 Steven P. Russo, Esquire 248 Washington Street Resident Inspector P. O. Box 1060 c/o U. S. NRC Toms River, New Jersey 08753 P. O. Box 445 Forked River, New Jersey 08731 Joseph W. Ferraro, J r., Esquire Deputy Attorney General Director, Criteria and Standards State of New Jersey Division Department of Law and Public Safety Office of Radiation Programs i
1100 Raymond Boulevard (ANR-460) i Newart, New Jersey 07012 U. S. Environtnental Protection l
Agency Ocean County Library Wasnington, D. C.
20460 Brick Township Branch 401 Chamcers Bridge Road U. S. Environ:: ental Protecticn Brick Tcwn, New Jersey 08723 Agency Region II Office Mayor ATTN: EIS C00RDINATOR Lacey Tcwnship 25 Fede 1 Plaza P. O. Box 475 New York, New York 10007 Forked River, New Jersey 08731 Comissioner Department of Public Utilities State of New Jersey 101 Comerce Street Newart, New Jersey 07102
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.%,.....f November 25, 1980 TO ALL POWER REACTOR LICENSEES WITH PLANTS LICENSED PRIOR TO JANUARY 1,1979 The Federal Register Notice enclosed with my letter dated November 24, 1980 has a typographical error in the effective date. The effective date should be February 17, 1981. A correction will be published in the Federal Register in the near future.
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l ENCLOSURE 2 1
OY!TER CREEK NUCLEAR GENERATING STATION, UNIT NO. 1 SUfM RY CF STAFF REQUIREMENTS TO RESCLVE OPEN ITEw.S COCKET NO. 50-219 3.1.23 Remote Shutdown Station In the Fire Protection Safety Evaluation Report, it was our concern that the present mathed of achieving safe shutdown by manual means may require as many as five opera-l tors. To resolve tnis concern we required that the licensee install a remote shut-down station that would be provided with adequate controls to shutdown tne plant from one location if a fire causes loss of the control room. Caoling for the re-mate shutdown station would be separated from existing cabling, and provided with adequate fire protection so that a fire will not cause loss of control from coth the control room and remote snutdown station. Mcwever, no infornation regarding this modification has been provioed to date.
'o meet Section III.G of Appendix R to 10 CFR Part 50, the licensee shall modify the design of the remote shutdown panel so that it can be isolated from the cable spreading room in such a way that a single fire would not incapacitate tne safe shutdown capability at both 1ccations.
3.2.5 Fire Hazards Analysis In the SER, it was our concern that the overall plant fire protection was not adequate and that a single fire could jeopardize safe shutdown systems. The licensee has not addressed this concern other than for those areas specifically identified elsewhere in the SER.
The licensee has not demonstrated that adequate protection features have been provided for cables and equipment of redundant systems important to achieving safe shutdown conditions to ensure that at least one means of achieving such conditions survives postulated fires.
To meet our fire protection guidelines, alternate shutdown caoability should be provided when safe shutdown cannot be ensured by barriers and detection and suppression systems because of the exposure of redundant safe shutdown equipment, cabling, or components in a single fire area, to an exoosure fire, or fire suppression activities, or rupture or inadecuate operation of fire suppression systems.
To meet Section III Paragraph G of Appendix R to 10 CFR Part 50, the licensee shall provide an alternate shutdown capability independent of this area. The alternate shutdown system shall meet the requirements of Section III Paragrach L of Appendix R to 10 CFR Part 50.