ML20135G627
| ML20135G627 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 11/25/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20135G608 | List:
|
| References | |
| NUDOCS 8509190596 | |
| Download: ML20135G627 (5) | |
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UNITED 5TATES 8(
NUCt. EAR REGULATORY CCMMissION c
WASHINGTON. D. C. 20SSS g,.b//. t 5*
SAFETY EVALUATION BY ~hE OFFICE OF HUCLEAR RE-C, TOR REGULATION SUPPORTING AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO. OPR-61 CONNECTICUT YANKEE ATOMIC POWER COMPANY t
HADDAM NECK PLANT DOCKET'NO. 50-213 INTRODUCTION
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Following a fire at the Browns Ferry Nuclear Station in March 1975, we initiated an evaluation of the need for improving the fire protection programs at all licensed nuclear power plants. As part of this continu-ing evaluation, in February 1976 we published a report entitled
- Recommendations Related to Browns Ferry Fire" NUREG-0050.
This report recommended that improvements in the areas of fire prevention and fire 4
coat-n1 be made in most existing facilities and that consideration ne given to design features that would increase the ability of nuclear facilities to withstand fires without the loss of inportant functions.
To implement the report's recemriendations, the NRC initiated a program for reevaluation of the fire protection programs at all licensed nuclear power stations and for a comprehensive review of all new ifcense i
applications.
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Ile have issued new guidelines for fire protection programs in nuclear power plants. These guidelines reflect the reconnendations in NUREG-0050.
These guidelines are contained in the following documents:.
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" Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," HUREG-75/087, Section 9.5.1. " Fire Protection," May 1976, which includes "Guicelines for Fire Protection l
for Nuclear Power Plants,' (BTP APCSB 9.5-1), May 1,1976.
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" Guidelines for Fire Protection for Nuclear Power Plants"(Appendix A to BTP APCSS 9.5-1), August 24 1976.
" Supplementary Guidance on Information Heeoed for Fire Protection Program Evaluation," Septemner 30, 1976.
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" Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls and Quality Assurance," June 14, 1977.
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s Connecticut Yankee Atomic Power Company has submitted a description of the fire protection program for the Haddam Neck Plant by letter dated february 22, 1977. This program is under detailed review by the NRC.
Ja the interim, until we complete our detailed review, we have concluded that it is appropriate to amend the facility license by incorporating into the Technical Specifications operaoility and surveillence requirements for the existing fire protection equipment and systems.
In addition, she amendment would include administrative requirements for the implementation of the fire protection program.
-ty letter dated December 1,1976, we requested the licenses to submit Technical Specifications for presently-installed fire protection equipment at this facility. The licensee responded by letter of February 25, i
1977.
Based on our review and consideration of the licensee's February 25, 1977 response and the responses of other licensees, we modified certain
. action statements and surveillance frecuencies in order to provide more appropriate and consistent specifications which we fon.arded to the licensee by letter of June 17, 1977 That letter also requested submittal of appropriately revised specifications.
The licensee resoonded by letters dated July 20 and October 18, 1977.
We have reviewed the licensee's response and have made modifications where necessary to assure conformance to the fullest extent practicable erith our requirements as set forth in the sample Technical Specifications pending completion of our ongoing detailed review of fire protection at this facility.
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. Jie have reviewed the licensee's proposed interin Technica ur requirements as implemented in the sampleW i
- ations aga nst o Technical Specifiestions.
the licensee in orcer specifications that'were proposed by One of the proposed to inske them confom to our recuirements.
specifications that we changed involves the minimum s ht me did not identify the numoer of mencers on a fire brigade t a en-site fire brigade.
We have now concluded that minimumfive (5).
w would find acceptaDie.
mumber for a typical comercial nuclear power p Shift Size."
.,$ER entitled " Staff Position Minimum Fire Brigade In the report of the Special Review GroJo on the Browns Fe (WREG-0050) dated Febntary 1976, consideration of :ne sa operation of all operating nuclear power plants pending the completion of.our detailed fire protection evaluation was p The following quotations from tne report sumarize tne basis for conclusion tnat.the operation of the plants, until' w complete ou d safety of feriew, does not present an undue risk to the health an she public.
'A probability assessment of public safety or risk in i
quantitative terms is given in the Reactor Safety Study l
As the result of the calculation based l
on the Browns Ferry fire the stuoy concluces tnat the (WASH.1400).
potential for a significant release of racioactivity from such a fire is about 20% of Inat calculatro fro This indicates tnat precicted
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potential accident risks from all causes were not greatly f,
affected by consideration of tne Browns Ferry fire.
This is one of the reasons that urgent action in regard to redir.ing rists due to potential fires is not recuirec.
The study (WASH-1400) alio' poin'ts out that 'rather straign -
forward measures, suen as may alreaoy exist at other auclear plants, can significantly re:uce tne li i
i a large fire.' The Review Group agrees.
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" Fires occur rather frequently; however, fires involving equipment unavailability comparable to the Browns Ferry fire are quite infrequent (see Section 3.3 [of NUREG-0050]).
The Revies Group believes that steps already taken since March 1975 (see Section 3.3.2) have reduced this frequency significantly.
" Based on its review of the events transpiring before.
during and after the Browns Ferry fire, the Review Group concludes that the probability of disruptive fires of the magnitude of the Browns Ferry event is small, and D-that there is no need to restrict operation of nuclear power plants for public safety. However, it is clear that much can and should be done to reduce even further the likelihood of disabling fires and to improve assurance of rapid extinguishment of fires that occur. Consideration should be.given also to features that would increase further the ability of nuclear facilities to withstand large fires without loss of important functions should such fires occur."
Subsequent to the Browns Ferry fire and prior to the Special Review Group's investigation, the Office of Inspection and Enforcement took steps with regard to fire protection.
Special bulletins were sent to all Itcensees of operating power reactors on March 24, 1975, and April 3,1975, directing the imposition of certain controls over fire
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ignition sources, a review of procedures for controlling maintenance
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and modifications that night affect fire safety, a review of emergency procedures for alternate shutdown and cooling methods, and a review of flamability of materials used in floor and wall penetration seals.
Special inspections covering the installation of fire stops in electrical' cables and in penetration seals were completed at all operating power reactors in April and May 1975. Inspection findings which reflected non-compliance with NRC requirements resulted in requiring corrective-action by licensees. Folicw-up 1,nspections have confirmed that licensees
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are taking the required corrective actions and that administra,tive control procedures are in place.
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6-Since these inspection activities and the subseauent Special Review Sroup recoceendations in the 1975 to 1976 time period, there has been no new infomation to alter the conclusions of the Special j
Review Group, ands the ongoing fire protection program flowing from l
1 those conclusions is still acequate.
Therefore, we have found these specifications acceptable on an interim basis until such time that our overall review is complete, required equipment is installed and operaole, and final specifications have teen developed and issued.
l DVIRONMENTAL CONSIDERATION Afe have determined that the planned amendment does not authorize a change in affluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this detemination, we nave further concluoe of envirernental impact and pursuant to 10 CFR 551.5(d)(4) that an efivironmental impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of this planned amenoment.
CONCLUSION _
Jie have concluded, based on the considerations discussed above, that:
(1) because the amencment ooes not involve a significant increase in the probability or consecuences of accicents previously consicered and does not involve a significant cecrease in a safety margin, the ameneent does not involve a significant nazarcs consiceration, (2) e
.there is reasonanle assurance tnat the health and safety of the public will not be endangertm ey operation in the proposeo manner, ano (3) suth activities will be concucted in c:::::pliance with the Coenission's regulations and the issuance of this plannec'amencment w of the public.
4S Date: November 25.'1977
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