ML19319C165
| ML19319C165 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/01/1977 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 287, NUDOCS 8001310523 | |
| Download: ML19319C165 (5) | |
Text
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NRC DISTRIBUTION roR PnRT 50 DOCKET MATERI AL TO:
FROM:
oATE oF DOCUMENT Toledo Edison Company 6/1/77 Mr John F. Stol:
Toledo, Ohio o,7s ages,yg o 6/6/77 Lowell E. Roe hervTER ONoToRIZED PROP (NPUT FORM NUMBER or COPIES RECC4VED doRio'NAL MNCLAssiriEo O cor n
/ 5 / 64/ dW DESCRIPTION ENCLOSU RE Amdt. to OL/ change to Acpendix A tech specs..to allow for. proper opera $1on of containment isolation valves for surve.111ance testing & unit operation under administrative control when in Operation Modes 1, 2, 3 or 4......
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Serial No. 287
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Attn:
Mr. John F. Stolz, Chief i
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United States Nuclear Regulatory Commission O
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Dear Mr. Stolz:
As discussed with your Licensing Project Manager, Mr. Leon Engle, your Mr. Jack Roe, our Mr. F. R. Miller and our Mr. G. L. Hurrell, in a telephone conversation on May 26, 1977, it was agreed by all that the following correction needs to be made to Table 3.6-2 of the Davis-Besse Nuclear Power Station, Unit No. 1 Techn. cal Specifications (Appendix A to Operating License !&F-3).
Add asterisk (*) to:
Penetration No.
Valve No.
29 DH 11 29 DH 23 39 MS 107 39 MS 107A 40 MS 106 40 MS 106A 57 MS 603 57 MS 603A 58 MS 611 58 MS 611A 74C DH 2735 74C DH 2736 Delete asterisk (*) from:
Penetration No.
Valve No.
25 SA 536 25 SA 532 26 SA 535 THE TCLEDO ECISCN COMPANY ECISCN PLAZA 3CO MADISCN AVENUE TOLECO, CHIO 43E52
Director of Nuclear.. actor Regulation Page 2 June 1, 1977 Serial No. 287 These asterisks (*) were omitted or added incorrectly by administrative error during development of the Technical Specifications.
We request that these changes be made to the Technical Specifications to allow for proper operation of these containment isolation valves for surveillance testing and unit operation under administrative centrol when in Operation Modes 1, 2, 3 or 4.
A safety evaluation for these requested changes is attached and is a part of this request.
These changes are urgently required to permit continued progression of startup testing and your prompt action is requested.
Yours very truly, M
Lowell E. Roe Vice President Facilities Development LER.r
Attachment:
Safety Evaluation
DB-1 SAFETY EVALUATION FOR REQUESTED CHANGE TO THE DB NPS UNIT 1 TECHNICAL SPECIFICATIONS (App. A to License No. NPF-3)
The following changes need to be made to Table 3.6-2 of the Davis-Besse Nuclear Power Station, Unit No. 1 Technical Specifications (Appendix A to Operating License NPF-3) to allow for proper operation of these con-tainment isolation valves for surveillance testing and unit operation under administrative control when in Operation Modes 1, 2, 3 or 4.
Add asterisk (*) to:
Penetration No.
Valve No.
29 DH 11 29 DH 23 39 MS 107 39 MS 107A 40 MS 106 40 MS 106A 57 MS 603 57 MS 603A 58 MS 611 58 MS 611A 74C DH 2735 74C DH 2736 Delete asterisk (*) from:
Penetration No.
Valve No.
25 SA 536 25 SA 532 26 SA 535 The deletion of the asterisk from the valves below results in a more conservative technical specification because the valve could not then be opened when in Modes 1, 2, 3 or 4, thereby performing their containment isolation function. These valves need not be opened during Modes 1, 2, 3 or l
4 for any planned testing or operation.
l Penetration No.
Valve No.
mA b
i SAFETY EVALUATION (continued)
DH 11 must be opened during Modes 3 and'4 to allow the Decay Heat Removal Pumps to take suction from the Reactor Vessel providing Decay Heat Removal.
The Safety Evaluation of having DH 11 open is discussed in the following correspondence to the NRC: Serial Nos. 220, 260 and 271.
I DH 23 must be opened in the event that 2ne of either DH 11 or DH 12 cannot be opened, and decay heat removal is required to cool down. The safety evaluation of this situation is discussed in the response to FSAR Position Number P 7.6.1 and in letter, Serial No. 242, dated March 21, 1977.
MS 107, 107A, 106 and 106A are opened to perform surveillance requirement 4.7.1.2 a 1 on the Auxiliary Feed Pump Turbine every 31 days. With regard to a postulated steam line accident, the SFRCS would align the valves to their required position to meet the accident requirements even if the surveillance test were being performed.
These valves are remote manual valves meeting the design requirements of GDC 57.
MS 603, 603A, 611 and 611A must be opened when in Modes 3 and 4 to control the steam generator level without concentrating the contaminants in the condensate in the steam generators. Discharge from these lines go to the i
condenser where the water is used in the condensate and feedwater system.
These valves meet containment isolation design criteria GDC 57 (Appendix A to 10 CFR 50) since they are remote manual valves operable from the control room.
DH 2735 and 2736 must be opened when in Modes 3 and 4 after DH 11 and DH 12 4
or DH 23 and DH 21 have been opened to provide control of the RCS pressure using the pressurizer auxiliary sprays. The lines from these valves to the I
DER system are Seismic Category 1 and would not provide a leakage path if containment isolation were required, since the DHR system would be operating.
June 1, 1977 4
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