ML20039D983
| ML20039D983 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/21/1981 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20039D984 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.1.2, TASK-TM NUDOCS 8201060401 | |
| Download: ML20039D983 (4) | |
Text
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e BALTIMORE G AS AND ELECTRIC COMPANY l
P.O. BO X 147 5 B ALTIMOR E. M A R YL AND 21203 ARThun E. LunovALL,JR.
Vice Passsorsef
$UPPLT December 21, 1981 c)
//
Office of Nuclear Reactor Regulation RECEIVED U.S. Nuclear Regulatory Commission S
i Washington, DC 20555 JAN 5 1982> c sacalImunncasus ATTENTION:
Mr. Robert A. Clark, Chief NOME ** W E R Operating Reactors Branch #3 f
Division of Licensing N
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 Request for Amendments
REFERENCES:
a) NUREG-0737, " Post-TMI Requirements", dated October 31, 1980 b)
BG&E Letter dated July 21, 1981, from A. E. Lundvall, Jr.
to R. A. Clark s
Gentlemen:
Baltimore Gas and Electric Company hereby requests an Amendment to its Operating Licenses Nos. DPR-53 and DPR-69 for Calvert Cliffs Units 1 & 2, respectively, with che submittal of the enclosed proposed changes to the Technical Specifications.
The proposed Amendment (Attachment 1) is being requested in accordance with Reference (a) and amends current Technical Specifications to include the automatic initiatiot, of Auxiliary Feedwater to each Steam Generator for MODES 1 & 2 per item II.E.1.2 of reference (a).
Figure 3.7-1 of Attachment (1) is a new Figure generated by this proposed Amendment and represents limits imposed as a result of our undercooling and overcooling analysis upon automatic initiation of auxiliary feedwater.
The proposed Amendment (Attachment 2) is being requested in accordance with Reference (a) and revises current Technical Specifications to exclude the automatic initiation of Auxiliary Feedwater for MODE 3 per Item II.E.1.2 ik 90 8201060401 811221 h
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Mr. Robert A. Clark December 21, 1981 of Reference (a). Attachment (2) has been separated from Attachment (1) to eliminate any confusion by the Plant Operating Staff with respect to applicability of automatic initiation of auxiliary feedwater during heat-up and cooldown modes of operation.
Since such operations necessitate maneuvering AFW flow control valves, to facilitate maintenance of heat-up and cooldown limits on the reactor plant while maintaining adequate steam generator inventory, obviously the required settings of these valves per Attachment (1) are not applicable during such operations.
Attachment (3), designated Figure 3.7-(Later), is being submitted for your review. This curve is not to be considered a part of Attachment (1) at this time. Attachment (3) represents an example of a proposed curve correlating Steam Generator Pressure versus Auxiliary Feedwater Flow which will be submitted under a separate proposed Amendment to Technical Specifica-tion 3.7.1.2 at a later date. Attachment (3) will be empirically derived during the first available refueling outages for Units 1 & 2, currently scheduled for April 17, 1932, and January 1, 1983, respectively. This correlation will provide oome flexibility in performing future surveillance testing in as far as flow verifications may be performed at steam generator pressures other than that specified by Figure 3.7-1 of Attachment (1) and referenced in the Technical Specification Bases of Attachment (1).
In reference (b) we committed to performing tests to verify Attachment (3) data by January 1, 1982. Surveillance requirements 4.7.1.2.c.3 and 4.7.1.2.d of the proposed Amendment (Attachment 1), along with the Attach-ment (3) data require a reduction in power for a period necessary to set flow control valves on each unit.
To implement the proposed amendment, we intend te reduce power on each unit the first available weekend following approval of the proposed amend-ment. However, to minimi 3 the number of forced reductions in power required to meet subsequent surveillance testing, we request a date extension on observing surveillance requirements 4.7.1.2.c.3 and 4.7.1.2.d until the Attachment (3) data can be produced.
It it anticipated that the first available opportunity to perform the tests to produce Attachment (3) data will be during the scheduled refueling outages.
We, therefore, request, concurrently with these ament ents, e date extension of 30 days beyond the scheduled outage completion dates for Units 1 and 2 to submit the Attachment (3) data.
For Units 1 and 2 we anticipate submittal completion dates of August 9, 1982, and May 9, 1983 5 respectively.
Since this proposed amendment has been prescribed in NUREG-0737, which addresses generic post-TMI concerns, we feel the following comments should be considered in your review. The undercooling and overcooling analyses which resulted in the Technical Specifications of Attachment (1) were done with the objective of determining a flow setpoint which would allow a reasonable time for operator action before either of the following conditions occur:
Mr. Robert A. Clark 3-Decemb'er 21,:1981'
-(a) inadequate heat sink, due to insufficient AFW flow, or (b) safety. injection' actuation, due to excessive AFW flow..
The analyses were based or best estimate: assumptions which provided realistic results.
For example, plant systems were assumed to function
.normally, steam line or feed line breaks were not. assumed.to occur, uncertainties were based on reasonably conservative estimates as opposed to absolute theoretical worst case.
SAFETY COMMITTEE REVIEW These proposed changes to the Technical Specifications have beenreviewed by our Plant Operations'and Safety Review and Off-Site Safety and1 Review-Committees, and they have concluded that-implementation of these changes I
will not result in an undue risk to the-health and safety of -the public.
FEE DETERMINATION We have determined, pursuant to 10 CFR Part 170 Paragraph 170.22, that this Amendment request consists of Class III and Class I amendments for Calvert-Cliffs-Unit Nos. 1 and 2, respectively, an6, accordingly,.we are including BG&E Check No. A028356 in the amount of $4,400.00 to-cover the fee for this request.
Very truly yours
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Vice President - Supply
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Mr. Robert A. Clark December 21, 1981 STATE OF MARYLAND:
TO WIT:
CITY OF BAL'.'IMORE:
Arthur E. Lundvall, Jr., being duly sworn states that he is Vice Preside.at of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he executed the foregoing Amendment for the purposes therein set forth; that the statements made in said Amendment are true and correct to the best of his knowledge, information, and belief; and that he was authorized to execute the Amendment on behalf of said Cocporation.
A WITNESS my Hand and Notarial Seal.
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A J A r, t
Notary Public My Commission Expires:
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cc:
J. A. Biddison, Esquire G. F. Trowbridge, Esquire D. H. Jaffe, NRC R. E. Architzel, NRC l
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