ML19341C867
| ML19341C867 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/24/1980 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | YANKEE ATOMIC ELECTRIC CO. |
| References | |
| LSO5-80-11033, NUDOCS 8103040326 | |
| Download: ML19341C867 (4) | |
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UNITED STATES
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November 24, 1980 ep f
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50-29 Plant Name:
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TO ALL POWER REACTOR LICENSEES WITH PLANTS 8
LICENSED PRIOR TO JANtJARY 1,1979 si, The Comission published on November 19,1980 (45 FR 76602), a revised Section 10 CFR 50.48 and a new Appendix R to 10 CFR 50 regarding fire protection features of nuclear power plants.
The revised Section 50.48 and Appendix R will become effect1ve February 17, 1981, which is 90 days after publication. A copy of the Federal Register Notice is enclosed (Enclosure 1).
The provisions of Apcendix R that are applicable to the fire protection features of your f acility can be divided into two categories. The first category consists of those prov1sions of the Appendix that are recuired to be backfit in their entirety by the new rule, regardless of whether or not alternatives to the specific requirements of these Sections have been previously approved 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, 011 Collection Systems for Reactor Coolant Pump. The fire protection features of your facility must satisfy the specific requirements of these three Sections by the dates established by Paragraph 50.48(c), unless an exemption from the Appendix R requirements is approved by the Comission. You should note the provisions for tolling the time for completing 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 features of your f acility consists of requirements concerning the "open" items of previous NRC staff fire protection reviews of your facility. An ocen item is defined as a fire protection featura that has not been previously approved by the NRC staff as satisfying the provisions of Appendix A to Branch Technical Position BTP PCSB 9.5-1, as reflected in a staff fire protection safety evaluation report. The fire protection features of your facility that are in this category must satisfy the specific requirements of Appendix R by the dates established by Paragraph 50.48(c), unless an exemp-tion from the Appendix R requirements on those features is approved by the Comi s sion. is a summary listing of the open items concerning the fire protection features of your facility based on a review of our records.
Also included is our position on the specific requirements that ::Ust be satisfied in order to resolve these open items.
If you have any questions or disagree-l ments with this enclosure, please advise us within 30 days of your receipt of this letter.
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2, l Witn regard to the. ire protection modifications that have Deen previously approved by the NRC staff, Peragraph 50.48(d) s::ecifies a new schecule for their coapletion. This paragraph, when it becomes effective, will supersede the currently affective section of the regulations that temccrarily suspends cocpletion dates for previously approved fire protection modifications that are given in f acility license conditions (45 FR 71569, October 29,1980).
The Comission expects that all such modifications will be conpleted in accordance with this new schedule, unless an extension has been requested and granted by the Director of the Office of Nuclear Reactor Regulation
[see Paragraph 50.48(d)], or an exenotion has been requested and granted by the Ccmission pursuant to Section 50.12 of the Comission's regulations.
If you have previously requested extensions of dates for completion of modifications that are required by license conditions for your facility which were not approved, and you have determined 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 Comission action resulting from this rule are subject to the schedule of feas spec..'ied in 10 CFR 170.21.
If you have any questions concerning the subject matters of this letter, please contact the NRC Project Manager for your facility.
Sincerely,
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[OarrellG.Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
Enclosures:
1.
Notice - Fire Protection Rule 2.
Summary of Staff Require-ments to Resolve Open Items cc w/ enclosures:
See next page
Mr. James A. Kay November ?4, 1980 cc w/ enclosure:
Mr. James E. Tribble, President Yankee Atomic Electric Conaany 25 Research Drive Westborough, Massachusetts 01581 Greenfield Community College 1 College Drive Greenfield, Massachusetts 01301 Chairnan Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Energy Facilities Siting Council 14th Floor One Ashburten Place Boston, Massachusetts 02108 Director, Criteria and Standards Division Office of Radiation Prograns (ANR-460)
U. S. Environmental Protection Agency Vashington, D. C.
20460 U. S. Environmental Protection Agency Region I Office ATTN: EIS COORDINATOR JFK Federal Building Boston, Massachusetts 02203 Resident Inspector Yankee Rowe Nuclear Power Station c/o U.S. NRC Post Office Box 28 Monroe Bridge, Massa-husetts 01350
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November 25, 1980 TO ALL POWER REACTOR LICENSEES WITH PLANTS LICENSED PRIOR TO JANUARY l,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.
^^y Darrell G. Eisenhut. Director
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ENCLOSURE 2
SUMMARY
OF STAFF REQUIREMENTS TO RESOLVE OPEN ITEMS YANKEE ROWE 50-029 3.2.3 Alternate Shutdown Caoability In the Fire Protection Safety Evaluation Report it was our concern that in several ara &s of the plant, the physical separation of redundant safe shutdown systems is inadequate so that redundant systems could be damaged by a single fire, thus the possibility of affecting safe shtudown. We requested the licensee to provide.a dedicated shutdown system which was to be provided as part of the SEP review. To date no information has been received regarding this modification.
To meet Section III, Paragraphs.G and L of Appendix R to 10 CTR Part 50 the licensee should provide a dedicated shutdown system.
ADMINSTRATIVE CONTROLS 6.1 Organization A fire brigade of at least five members will be maintained on site at all times. However, the licensee has stated the Shift Supervisor will be the leader of the fire brigade.
It is our opinion that the Shift Supervisor should not be a member of the fire brigade because his presence may be necessary elsewhere if the fire occurs in certain critical areas of the plant. The brigade leader should not have other responsibilities that would distract him from his full attention being devoted to the fire. His total function should be to survey the fire area, command the brigade and keep upper level management informed.
We, therefore, conclude that this proposed use of the Shift Supervisor as fire brigade leader is un:c:aptable.
To meet Section III Paragraph H of Appendix R to 10 CFL Part 50, the licensee should revise the adninistrative controls secticn of his fire protection program to remove the Shift Supervisor from the fire brigade.