ML20032E659
| ML20032E659 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/16/1981 |
| From: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20032E660 | List: |
| References | |
| NUDOCS 8111200786 | |
| Download: ML20032E659 (3) | |
Text
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Wisconsin Electnc exta coursur 231 W. MICHIGA't, P.O. BOX 2046. MILWAUKEE. WI 53201 November 16, 1981 CERTIFIED MAIL D J'
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Mr. H.
R.
Denton, Director C > T-1k l%
Office of Nuclear Reactor Regulation (gi
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S. NUCLEAR REGULATORY COMMISSION g
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Washington, D.
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20555 6^' "o **O%'W
'l Attention:
Mr.
R.
A.
Clark, Chief
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Operating Reactors Branch 3 k
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@ JIo Gentlemen:
DOCKET NOS. 50-266 AND 50-301 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 72 REDUNDANT DECAY HEAT REMOVAL POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In accordance with the request in Mr. Robert A. Clark's letter dated August 14, 1981, Wisconsin Electric Power Company (Licensee) requests amendments to Facility Operating Licenses DPR-24 and DPR-27 for the Point Beach Nuclear Plant, Units 1 and 2, respectively.
The purpose of these amendments is to incorporate certain changes into the Technical Specifications to ensure redundancy of decay heat removal capability under all operating conditions.
In a letter dated June 11, 1980, the NRC requested Licensee to review the Point Beach Nuclear Plant Technical Specifications to ensure that redundancy of decay heat removal was provided under all operating conditions.
He responded, by letter dated October 14, 1980, that the existing Technical Specifications did address this concern and the Specifications required no changes.
Specific references to the Specifications were provided to support Licensee's determination.
In Mr. Clark's August 14 letter, the NRC agreed that for conditions corresponding to normal power operation, hot shut-down and refueling shut-down, the Technical Specifications provided for redundancy in decay heat removal capability.
However, for conditions corresponding to operational modes 4 and 5, that is at reactor coolant tempera-tures between 350*F and 140 F, the NRC again requested proposed Technical Specification changes be submitted.
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PDR ADOCK 05000266 P
Mr. H.
R.
Denton November 16, 1981 i
In response to this request, Licensee has proposed the attached Technical Specification changes.
Specific changes on each of the attached pages have been indicated by margin bars.
A discussion of these changes follow.
1.
Specification 15.3.1.A.l.b has been changed by substituting the terminology " rated power" for
" thermal power".
The specification, currently
~
written as "l% of thermal power", does not define i
a specific core thermal aucput.
2.
A new Specification 15.3.1.A.2 has been provided, modeled after the standardized technical speci-fications, to require redundant operable decay heat removal methods when reactor coolant tempera-tures are between 350*F and 140*F.
A section has also been included to clarify the decay heat removal requirements when the reactor coolant temperature is less than 140 *F and to specify a permissible operating condition to permit periodic maintenance of the residual heat removal system.
3.
The Basis for Specification 15.3.1.A has been modified to include a discussion of, and basis for, the new Specification 15.3.1.A.2.
4.
Specification 15.3.3.A.2 has been reworded.
As presently written, this Specification requires the reactor to be placed in a cold shut-down condition if a residual heat removal pump is out of service for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
This action results in putting the reactor coolant system in a condition without redundant decay heat removal capa-bility.
Therefore, the Specification has been rewritten to permit keeping the reactor in a h'.b standby condition with reactor coolant temperatures between 500'F and 350*F so that the steam generators may be used for redundant decay heat removal while the residual heat removal system is repaired.
5.
Specification 15.3.8.A.4 has been changed so that it is consistent with new Specification 15.3.1.A.2.
Reference is made to the entire residual heat removal loop rather than simply the pump.
This specific change was suggested by the MRC Staff.
A sentence has also been added to permit securing the operating residual heat removal loop for up to one hour in an eight hour period when flow would interfere with refueling operations.
Mr. H.
R. Denton November 16, 1981 In accordance with the provisions of 10 CFR Part 170.22, we have determined that since these Technical Speci-fication changes involve a single issue, redundant decay heat removal, for which an NRC position has been previously identified,this license amendment application should be classified as a Class III amendment.
The duplicate amendment for the second Point Beach unit may be classified as a Class I amendment.
Therefore, we have enclosed herewith a check drawn in the amount of $4,400 for the amendment approval fee.
As specified in the Commission's regulations, we are providing three signed originals and, under separate cover, forty copies of this license amendment application and attachments.
Should you have any questions concerning the contents of this application, please notify us so that we may address your concerns.
Very truly yours, 1
O Executive Vice President Sol Burstein Enclosures (Check No. 646108)
Copy to NRC Resident Inspector Subscribed and sworn to before me this /Ish day of November 1981.
&_WYW Notary Pdblic, State of Wisconsin My Commission expires,bSw /,/fTY.