ML20070P051
| ML20070P051 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/17/1983 |
| From: | Ash R BALTIMORE GAS & ELECTRIC CO. |
| To: | Jaffe D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20070P052 | List: |
| References | |
| NUDOCS 8301260084 | |
| Download: ML20070P051 (7) | |
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BALTIMORE GAS AND ELECTRIC CHARLES CENTER. P.O. BOX 1475 BALTIMORE, MARYLAND 21203 ELECTRIC ENGINEERING ornRrutur January 17, 1983 Office of Nuclear Reactor Regulation U.S. Juclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. David H. Jaffe Operating Reactors Branch #3 Divicion of Licensing
Subject:
Calvert Cliffs Nuclear Power Plant Unit No. 2, Docket No. 50-318 Auxiliary Feedvater Modifications The status of the auxiliary feedvater modifications for Unit 2 during the Fall 1982 Refueling Outage has been the subject of many phone conversations between yourself and our Messrs. L. Wenger and W. Holston.
As discussed, we anticipate construction and testing of the motor driven train vill be complete by the end of the outage.
At present, we vill not receive the spare parts for the motor driven pump until May, 1983 This could place us in a position where ve are not able to meet the Limiting Conditiori for Operation of Technical Specification 3.7 1.2.
With the motor driven pump disabled due to lack of spares, we vould face a significant period of loss of power production on Unit 2.
To mitigate the loss of availability on Unit 2, we have drafted i
the enclosed Technical Specification changes. These changes allow the operat. ion of the Unit with two operable steam turbine driven Auxiliary Feedvater pumps. The justification for these changes is included in the attached letter.
These changes have been reviewed by our management for an unreviewed safety question and approved. Should the need arise for their use, we would forward the attached letter and Technical Specification changes with check to your organization. This draft copy is for your advance information.
fool 8301260094 830117 PDR ADOCK 05000318 P
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Office of Nuclear Reactor Regulation January 17, 1983 Should you have any questions, feel free to contact us.
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R. F. Ash Supervising Engineer Nuclear Generation Engineering Section WCH/RFA/tej cc: Messrs. J. A. Biddison, Esquire G. F. Trowbridge, Esquire R. E. Architzel, NRC I
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DRAFT December 00,1982 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Cornmission Washington, D. C. 20555 ATTENTION:
Mr. Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing SUB3ECT:
Calvert Cliffs Nuclear Power Plant Unit No. 2 Docket No. 50-318 Request for Amendment
REFERENCES:
a)
Letter A. E. Lundvall, Jr. to R. A. Clark of November 5,1982 b)
Letter A. E. Lundvall, Jr. to R. A. Clark of November 17,1982 c)
Letter R. C. L. Olson to R. A. Clark of November 22,1982 Gentlemen:
The Baltimore Gas and Electric Company hereby requests an Amendment to its Operating License No. DPR-69 for Calvert Cliffs Unit No. 2, with the submittal of the enclosed proposed changes to the Technical Specifications.
Proposed Change (BG&E FCR 82-1052 Supplement 1)
Delete the following pages of the Unit 2 Technical Specifications and add new pages as indicated:
a) delete page B7-2 and add new page B7-2, Attachment 1 b) delete page 3-21 and add new page 3-21, Attachment 2 c) delete page 3-41 and add new page 3-41, Attachment 3 d) delete page 7-5 and add new page 7-5, Attachment 4 e) delete page 7-5a and add new 7-5a, Attachment 5
Mr. R. A. Clark December 00,1982 Page 2 DISCUSSION AND JUSTIFICATION Reference (a) forwarded Technical Specification changes, necessary to implement our Third Train Auxiliary Feedwater Modifications. These modifications were implemented to meet the Post TMI Requirements for Operating Reactors (NUREG-0737 TMI action plan), item II.E.1.2 and the NRC Action Plan developed as a result of the TMI-2 Accident (NUREG-0660, Vol. 1).
As discussed in reference (a) a major portion of these modifications involved the installation of a new electric driven pump train and associated controls. Reference (b) forwarded a reanalysis of those Design Basis events which were affected by these modifications. The accidents analyzed included the Main Steam Line Break, Feedline Break, and Loss of Feedwater events. Reference (c) included an updated Piping and Instrument Diagram and the Auxiliary Feedwater Actuation System Logic Program.
The above referenced technical specifications were submitted with the Unit 2 Cycle 5 reload submittal to enable startup of Unit 2 following modifications performed on the AFW System during the Fall 1982 refueling outage. At the present time we are not able to meet the Limiting Condition for operation of Technical Specification 3.7.1.2 due to a failure of the motor driven pump. We do not expect the spare parts necessary to repair the pump to be available until *.
To allow continued operation with an inoperable motor driven train, the enclosed changes to the Technical Specification will be necessary. These changes delete the requirement to maintain the motor driven pump operational. In this case the AFW system design will rely on two steam driven pumps, with the following provisions as discussed below. We
o Mr. R. A. Clark December 00,1982 Page 3 consider these changes to be of a temporary nature and the present technical specifications would be resubmitted upon repair of the motor driven pump.
Our justification for submitting these changes are as follows:
(1)
Calvert Clifis was licensed and operated safely with two turbine driven Auxiliary Feedwater pumps prior to the Unit 2 Cycle 5 reload.
During the Auxiliary Feedwater modifications significant improvements were incorporated into the original design. Therefore, the steam driven train is more reliable than the original design. These changes include:
a.
The steam inlets to the Auxiliary Feedwater pump turbines are now fail "open" control valves.
Previously they were fall "as is" motor operated valves. With a loss of off site power we will now have steam flow to the pumps without requiring operator action.
b.
The Auxiliary Feedwater Actuation Signal is generated from the newly installed Wide Range Steam Generator Level Indication System.
The automatic signal to start the pumps will therefore result in less unnecessary challenges to the system. The narrow range utilized before resulted in an actuation signal with each reactor trip due to steam generator shrink levels.
c.
The flow control valve in the discharge line was modified in order to maintain a ccnstant Auxiliary Feedwater flow regardless of steam generator back pressure.
This feature reduces the possibility of an overcooling or undercooling transient.
d.
Two air to close, fall open valves were installed in series in each steam generator Auxiliary Feedwater flow leg. These valves automatically shut, via
Mr. R. A. Clark December 00,1982 Page 4 independent signals, when a ruptured generator occurs.
Detection logic has been installed to provide the operator in the control room e.
with indication that an Auxiliary Feedwater discharge piping rupture has occurred. The operator can then take rapid action to isolate the ruptured line and direct additional flow as necessary via the intact line.
2.
The Design Basis events issued in reference (b) were evaluated in light of the proposed change and were found still valid. The number of available Auxiliary Feedwater flow legs is cut in half by isolating the motor driven pump.
It is therefore necessary to double the flow control valve setpoint of the two remaining steam driven pump legs from that value found in the Technical Specifications in reference (a).
3.
The Action statement for the motor driven pumps in the present technical specification (reference (a)) requires that the plant be shutdown until repairs can be completed.
This outage would create a sipific,.t. t financial impact on our company.
These proposed Technical Specification changes do not constitute an unreviewed safety qut.stion. The Bases for the Auxiliary Feedwater Technical Specification as forwarded in reference (b) have changed but the overall quantity of Auxiliary Feedwater flow to the steam generators is not reduced. A review of the Auxiliary Feedwater Analyses has shown that the proposed change will not present an undue risk to the health and safety of the public.
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s Mr. R. A. Clark December 00,1982 Page 5 SAFETY COMMITTEE REVIEW This proposed change to the Technical Specifications has been reviewed by our Plant Operations and Safety and Off-Site Safety Review Committees, and they have concluded that implementation of this change will not result in an undue risk to the health and safety of the public.
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FEE DETERMINATION We have determined, pursuant to 10 CFR Part 170, Paragraph 170.22, that this Amendment request consists of a Class III amendment for Calvert Cliffs Unit No 2, and accordingly, we are including BG&E Check No.
In the amount of $4,000.00 to cover the fee for this request.
4 Should you have further questions regarding this matter, please contact us.
BALTIMORE GAS AND ELECTRIC COMPANY By:
Vice President-Supply cc:
- 3. A. Biddison, Esquire G. F. Trowbridge, Esquire D. H., Jaffe, NRC R. E. Architzel, NRC
- Date to be supplied if pump fails.
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