ML19340E526
| ML19340E526 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/24/1980 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | ALABAMA POWER CO. |
| References | |
| NUDOCS 8101140822 | |
| Download: ML19340E526 (3) | |
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ro November 24,15?]
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Docket 1c. 50-348 Plant Nace:
Joseph M. Farley Unit No.1 l
TO ALL POWER REACTOR LICENSEES WITH PLANTS LICENSED PRIOR TO JANUARY 1,1979 Tne Coanission published on November 19,1980 (45 FR 76602), a revised Sec-ion 10 CFR 50.48.and a new Appendix R to 10 CFR 50 regarding fire prctection features of nuclear power plants. The revised Section 50.48 anc Appendir R vill become effective February 17, 1981, which is 90 days after publica ion. A copy of the Federal Register Notice is enclosed
(:n:losure 1).
Tne provisions of Appendix R that are applicable to the fire protection fea ures of your facility can be divided into two categories.
The first category consists of those provisions of the Appendix that are reouired to se backfit in their' entirety by the new nale, regardless of whether or not alternatives to the specific requirements of these Sections have been previously approved by the NRC staff. These requirements are set forth in Sections III.G, Fire Protection of Safe Shutdown Capability; III-J,
,, E ergency Lighting; and III-0, Oil Collection Systems for Reactor Coolant Pune. The fi7 crotection features of your facility must satisfy th; 5:ecific regt
- -ts of these three Sections by the dates established by 3aragraph x mc), unless an exemption from the Appendix R requirements is approved by the Comission. You should note the provisions for tolling the time for conpleting the modifications required by these three Sections of Appendix R set forth in Paragraph 50.48(c)(6).
The second category of Appendix R provisions applicable to the fire protection fea ures of your facility consists of requirements concerning the "open" items of Orevious NRC staff fire protection reviews of your fa.:ility. An open ite: is defined as a fire protection feature that has not been previously approved by the NRC staff as satisfying the provisions af Appendix A to Branch Technical Position BTP PCSB 9.5-1, as reflected
.'n a staff fire protection sahty evaluation report. The fire protectio.1 features of your f acility that are in this category nust satisfy the specific requirements of Appendix R by the dates established by Paragraph 50.48(c), unless an exenp-tion from the Appendix R requirements on those features is approved by the Cormi ssion. is a summary Usting of the open items concerning the fire l
pec ettien features of your facility based on a review of our records. Also
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inclur is our position on the specific requirements that nLst be satisfied in Orde, to resolve these open items.
If you have any questions or disagree-Ter s witn this enclosure, please advise us within 30 days.of your receipt of nis letter.
t 8101140 1
. kitn regard to the fire protection modifications that have been previously approved by the NRC staff, Paragraph 50.48(d) soecifies a new schedule for their completion. This paragraph, when it becomes effective, will supersede the currently effective section of the regulations that tencorarily suspends concletion dates fer previously approved fire protection modifications that are given in facility license conditions (45 FR 71569. October 29,1980).
The Comission e-pects that all such modifications witl be cocpirDd in accordance with this new schedule, unless an extensior has been requested and granted by the Director of the Office of Nuclear Feactor Regulation
[see Paragraph 50.48(d)], or an exemotion has been recuested and granted by the Comission pursuant to Section 50.12 of the Comidsion's regulations.
If you have previously requested extensions of dates for completion of codifications that are required by license conditions for your facility which were not approved, and you have deterMned that these extensions are still necessary and justifiable, it will be necessary for you to reapply for any such extensions in accordance with the provisions of Paragraph 50.48(d).
. All requests for Connission action resulting from this rule are subject to the schedule of fees specified in 10 CFR 170.21.
If you have any cuestion', concerning the subject matters of this letter, please contact the NRC Project Manager for ycur facility.
Sincerely,
[ % du.3 c k ]& <E -
g Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Enclosu*es:
1.
Notice - Fire Protection Rule 2.
Summary of Staff Require-ments to Resolve Open Items cc w/ enclosures:
See next page
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S'JU'.4RY OF STAFF REQUIREMENTS TO RESOLVE OPEN ITEMS J. M. FARLEY, UNIT 1 DOCKET NO. 50-348 Alternate Shutdowm System In the Fire Protection Safety Evaluation Repart (paragraph IV.A) it was our concern that in several areas redundant systems could be damaged by a single fire, thus the possibility of affecting safe shutdown.
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 capability 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 exposure fire, or fire suppression activities, or rupture or inadequate operation of fire suppression systems.
To meet Section III, Paragraph G of the Appendix R to 10 CFR Part 50, the licensee should provide an alternate shutdown capability for the following areas of the plant:
1.
Control Room 2.
Cable Spreading Room The alternate shutdown systems should meet the requirements of Section III, Paragraph L of Appendix R to 10 CFR Part 50.
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November 25, 1980 TO ALL POWER REACTOR LICENSEES WITH PLANTS LICENSED PRIOR TO JANUARY l,1979 Tre Federal Register Notice enclosed with my letter dated t'ovember 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 Reoister in the near future.
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Darrell G. Eisenhut. Director O'
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Division of Licensing Ci 0~
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