ML19208A602
| ML19208A602 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/09/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19208A596 | List: |
| References | |
| NUDOCS 7909170063 | |
| Download: ML19208A602 (2) | |
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/590-01 UNITED STATES NUCLEAR REGULATORY COM ISSION DOCKET NO. 50-10 COMMONWEALTH EDIS0N COMPANY NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (the Conmission) has issued Amendment No. 30 to Facility Operating License No. DPR-2 to Conmonwealth Edison Company (the licensee), which amended the license for operation of the Dresden Nuclear Power Station, Unit No.1 (the facility) located in Grundy County, Illinois.
This amendment will become effective twenty days after issuance, unless a hearing has been requested.
This amendment adds license conditions relating to the completion of facility modifications for fire protection and the implementation of administrative controls.
The Commission has made appropriate findings as required by the Atomic Energy Act of 1954, as amended, and the Cormission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Prior public notice of this amendment was not required since the amendment does not involve a significant hazards consideration.
The Conmission has determined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
1909'70 Sti1157
6 7590-01 For further details with respect to this action, see (1) the licensee's submittals dated October 8,1976, November 30, 1976, December 28, 1976, March 17,1977, March 29,1977, July 19,1977, March 20,1979, May 30,1979, and July 5, 1979, (2) Amendment No. 30 to License No. DPR-2, including the Commission's letter of transmittal, and (3) the Comission's related Safety Evaluation.
All of these items are available for public inspection at the Comrnission's Public Document Room,1717 H Street, N. W., Washington, D. C. and at the Morris Public Library, 604 Liberty Street, Morris, Illinois 60451.
A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C.
- 20555, Attention: Director, Division of Operating Reactors.
Dated at Bethesda, Maryland, this August 9,1979.
FOR THE NUCLEAR REGULATORY COMMISSION O
Wq
'n d Dennis L. Zieman Chief Operating Reactors Branch #2 Division of Operating Reactors 301158
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,m BROOKHAVEN NATIONAL LABORATORY ASSOCIATED UNNER$lilES, INC.
Leten New Mrx 11073 Mc-rr ent Of Nuc' ear Erergy (516)2 f 2144 July 3, 1979 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Robert L. Fe, guson Plant Systems Branch i ldt Cear Bob:
Subject:
Fire Protection in Operating Nuclear Power Stations Dresden-1 Safety Evaluation Report Review The Safety Evaluation Report, as developed jointly by the NRC staff and 3rcokhaven National Laboratory (BNL), adequately reflects the concerns and recom-mendations of the consultants.
Throughout the reevaluation of Dresden-1, there has been general agreement between the NRC staff and the BNL consultants.
Based on present data, the proposed fire protection, as set forth in the SER, will give reasonable assurance that the health and safety of the public is not endangered.
The following exception represents a differing engineering point of view that should be evaluated by the NRC staff.
Valve Sucervision - Section 4.3.1 Electrical valve supervision should be provided on all valves centrolling fire water systems and sectionali:ing valves.
The present proposal of 3 2in-istrative controls cr locks is unacceptable.
See letter dated July 13, '.977 to Ur. R.
w.
Ferguscn frCm Mr. R. E. Hall.
Vertilation System - Section 4.4.1 Tec ; resent ;;crtable system consists cf two 5200 CFM fans with ducting, 3r.d acditional pertable units available from the local fire department. We reccrrend an additional 52C0 CFM be on hand at the site to be more consistent ith the BL recccrended minimum portable ventilation.
- nterior Fcse Stations - Section 4.2.1.4 We reccTend replacing the 1-1/2" no::les with " Class C, all-spray electric tyce no::les ' where electrical shock hazard is a consideration for personnel safety.
A suitable alternative is 1-1/2" adjustable no::les providing a spray strer ;attern without going through the straight stream made to open or close tFe no::le.
S51159 60&
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'00R ORGINAL
.. Ferguson July 3. 1 0 The preceding statements are based on a detailed reevaluation of the fire protection program as implemented by the Commonwealth Edison Co. at the Dresden-1 Nuclear Power Station. The analysis covered a review of the fire prevention, detection and suppression capabilities of the plant as interfaced with the nuclear systems requirements. This was accomplished by utilizing a review team concept with members from Brookhaven National Laboratory and the Nuclear Regulatory Comission Division of Operating Reactors staff.
The fire protection evaluation for the Dresden-1 Plant is based on an anal-
/si s of documents submitted by the Cerronwealth Edison Co. to the Nuclear Pegula-tory Ccmission and a site visit. The site visit was conducted by Fessrs.
Cunning and L. Cerderian of the NRC; Fr. M. Antonetti of Gage Babcock &
- r. J.
Rs:ciates, Inc., under contract to Brookhaven National Laboratory, and v niccelle, consultant to BNL.
"r. Riopelle was under contract to 5NL to review
?ne manual firefighting capabilities of the station, along with administrative controls.
The Dresden-1 review has been conducted under the direction of Fr. E. A.
We have
% cCougall and myself of the Peactor Engineering Analysis Group at BNL.
r? vie.ed the analyses submitted by the licensee and have visited the facility to emine the relationship of safety-related components, systems and structures with both conbustibles and the associated fire detection and suppression systems.
Our review has been limited to the aspects of fire protection related to the iratection of the public from the standpoint of radiological health and safety.
We have not considered aspects of fire protection associated with life safety of onsite personnel and with property protection, unless they impact the health and u fety of the public due to the release of radioactive material.
The proposed modifications represent a significant increase in the level of protection against sericus fire associated hazards.
Respectfully yours, l
J M c&mi fcbert E. Hall, Gr:up Leader React:r Engineering Analysis
^2 E2M/dt 951.L60