ML20203G264
| ML20203G264 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 07/29/1986 |
| From: | Frank Akstulewicz Office of Nuclear Reactor Regulation |
| To: | Opeka J CONNECTICUT YANKEE ATOMIC POWER CO. |
| References | |
| NUDOCS 8608010046 | |
| Download: ML20203G264 (5) | |
Text
_
July 29,1986 Docket No.
50-213 Mr. John F. Opeka, Senior Vice President Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Post Office Box 270 Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING AUTOMATIC DIESEL LOADING FOR CHARGING PUMPS AND ACCEPTANCE CRITERIA FOR CONTAINMENT AIR RECIRCULATION FILTRATION SURVEILLANCE TESTS Re:
Haddam Neck Plant By letter dated October 20, 1981, Connecticut Yankee Atomic Power Company requested changes in the technical specifications to remove the charging pumps from the automatic diesel loading sequence and to revise the acceptance criteria for the containment air recirculation fan filters. After review of the submitted materials and discussions with the licensee's staff, we conclude that there is inadequate information for us to complete our review.
contains requests for additional information in the two subject areas.
Within 10 working days of receipt of this letter, we request that the licensee provide the project manager with a schedule for responding to the enclosed information requests. We understand that the ongoing technical specification conversion will also incorporate these requested changes and therefore, resolution of these issues should be a high priority prior to submittal of the conversion package.
Sincerely, Original signed by:
F. Akstulewicz Francis M. Akstulewicz, Jr.
Integrated Safety Assessment Project Directorate Division of PWR Licensing - B
Enclosure:
DISTRIBUTION As Stated Docket File. '
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j WASHINGTON, D. C. 20555 July 29,1986 Docket No.
50-213 Mr. John F. Opeka, Senior Vice President Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Post Office Box 270 Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING AUTOMATIC DIESEL LOADING FOR CHARGING PUMPS AND ACCEPTANCE CRITERIA FOR CONTAINMENT AIR RECIRCULATION FILTRATION SURVEILLANCE TESTS Re:
Haddam Neck Plant By letter dated October 20, 1981, Connecticut Yankee Atomic Power Company requested changes in the technical specifications to remove the charging pumps from the automatic diesel loading sequence and to revise the acceptance criteria for the containment air recirculation fan filters. After review of the submitted materials and discussions with the licensee's staff, we conclude that there is inadequate information for us to complete our review.
contains requests for additional information in the two subject areas.
c.
Within 10 working days of receipt of this letter, we request that.the licensee provide the project manager with a schedule for responding to the enclosed infomation requests. We understand that the ongoing technical specification conversion will also incorporate these requested changes and therefore, iy resolution of these issues should be a high priority prior to submittal of the conversion package.
Sincerely; Francis M. Akstulewicz, r.
Integrated Safety Assessment Project Directorate Division of PWR Licensing - B
Enclosure:
As Stated cc:
See Next Page
1 Mr. John F. Opeka Connecticut Yankee Atomic Power Company Haddam Neck Plant l
cc:
Gerald Garfield, Esquire Kevin McCarthy, Director Day, Berry & Howard Radiation Control Unit i
Counselors at Law Department of Environmental City Place Protection Hartford, Connecticut 06103-3499 State Office Building Hartford, Connecticut 06106 Superintendent Haddam Neck Plant Richard M. Kacich, Supervisor RDF #1 Operating Nuclear Plant Licensing Post Office Box 127E Northeast Utilities Service Company East Hampton, Connecticut 06424 Post Office Box 270 Hartford, Connecticut 06141-0270 Edward J. Mroczka Vice President, Nuclear Operations Northeast Utilities Service Company Post Office Box 270 Hartford, Connecticut 06141-0270 Board of Selectmen Town Hall Haddam, Connecticut 06103 i
State of Connecticut Office of Policy and Management
?
ATTN: Under Secretary Energy Division 80 Washington Street Hartford, Connecticut 06106 i
Resident Inspector Haddam Neck Nuclear Power Station c/o U.S. NRC East Haddam Post Qffice East Haddam, Connecticut 06423 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 f
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REQUEST FOR ADDITIONAL INFORMATION CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT A.
Technical Specification Section 4.3 1.
Explain the bases for removing the charging pumps from the emergency diesel generator (EDG) automatic load sequencing and provide the technical analyses that support acceptability for handling the spectrum of small break LOCAs.
Include analysis for bringing charging pumps on line in timely fashion.
Explain how this affects overall plant safety.
2.
Provide the analysis showing that the charging pumps can be restarted in -time to mitigate the consequences of a small break LOCA if a loss of offsite power occurs during charging pump operation.
3.
Describe changes to be made to the electrical power supply and logic circuitry for the charging pumps and EDG automatic load sequencing as a result of this TS change.
4.
Discuss procedural changes including emergency response procedural changes, to be made as a result of this TS change.
5.
Discuss changes to be made for surveillance testing of the charging
~
pumps, the power supply and logic circuitry associated with this TS change.
B.
Technical Specification Section 4.4 Item 5 of your October 20, 1981 letter states, with respect to the fan filters,,"The proposed change maintains the same level of safety as the present Technical Specifications as the overall efficiency of the filters remains the same". Provideyourbases(analysis)thatsupports this statement. As part of your response provide the following information:
1.
Provide details of the design basis for the adsorber iodine removal capacity selected, specifically:
a.
Assumptions on the rate of release of iodine from the l
primary system into containment following the accident (instantaneous release of inventory or a specified l!
release rate).
b.
Any assumed iodine removal mechanism from containment air (other than the adsorber).
c.
Total flow rate through the adsorber.
4
_2 d.
Release rate assumed from containment.
e.
Use and effectiveness of demisters upstream of the adsorber banks.
f.
The minimum time required for reduction of iodine concentration in containment to " acceptable" levels, if this is a consideration. Discuss and provide the " acceptable" levels.
2.
Provide your analysis showing any effects (increases) in iodine release to the site boundary as a result of this change and show that 10 CFR Part 100 limits will not be exceeded.
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