ML20029A424

Rev 3 to Selected Licensee Commitments manual.W/910214 Ltr

ML20029A424
Person / Time
Site:	Catawba
Issue date:	02/28/1991
From:	Tuckman M DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PROC-910228, NUDOCS 9102220064
Download: ML20029A424 (6)

Text

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DUKEPOWER February 14, 1991 T U.S. Nuclear Regulatory Commission Attention: Document Control Desk

Washington, D.C. 20555 L

Subject:

Catawba Nuclear Station Docket No. 50-413 and 50-414 Selected Licensee Commitments Manual _

Gentlemen:

Pursuant-to 10 CFR 50.4 and 50.71, please find attached 10 copies of numrast

, Revision 3 dated 2/91 to the Catawba Selected Licensee Commitments :7%

- Manual. The SLC Manual is Chapter 16.0 to the Catawba FSAR. This

'v al; d manual is meant to contain commitments and other station issues that

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we believe warrent higher control, but are not appropriate in the oin f!g9ify k Technical Specifications (TS). Instead of being updated with the M annual FSAR Update, the SLC Manual will be updated as needed during r ._the year, 1

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Very truly ours, EE E

r M.S. Tuckman JAR / jar Attachment-I l Mr Stewart D. Ebneter xt:

Regional Administrator, Region 11 l

-U.S. Nuclear Regulatory Commission

.101 Marietta Street, NW, Suite 2900 .

I Atlanta, Georgia 30323 -

k 7h, Mr. W.T. Orders- ,

I NRC Resident inspector l l P Catawba Nuclear Station J

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- Februaryc14',' 1991 0 ,

Subject:

Catawba Nuclear; Station,~ Units l'and 2 Selected Licensee Commitments Manual

Revision 3 dated 2/91

)

Please findiattached a copy of Revision 3 dated 2/91 to 'he subject

. manual.

1. . Update your; manual as'follows:

Remove thete pages- Insert these pages

, LOEP-1,2~ L0EP 1,2 s16;10-l'- - 16.10-1 116.10-2. , - 16.10 .lf=youLhavelanyl questions, please contact me at 373-7567.

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-R.L. Gill l Jr.,.. Technical System Manager

' Regulatory Compliance o

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egulatory Compliance-l d ': ,

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DUKE POWER COMPANY l

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CATAWBA NUCLEAR STATION-

-SELECTED LICENSEE COMMITMENTS MANUAL  :

I LIST OF EFFECTIVE PAGES Page Revision Date L0EP 1 2/91 l LOEP 2 2/91 i LOEP 3 7/90 Tab 16.0 16.0-1 12/90 Tab 16.1 16.1-1

Tab 16.2

'16.2-1 ex Iq_,) . :16.2-2 1/91 16.2-3 Tab 16.3 Tab 16.4 Tab 16.5-

~

Tab 16.6 Tab 16.7.

Tab 16.8

-Tab 16.9 16.9-0 12/90-16.9-1 12/90 16.9-2' 12/90 g s,_ 16.3-3 12/90 16.9-4 12/90 Page 1 2/91

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O Page Revision Date 16.9-5 12/90 16.9-6 12/90 16.9-7 12/90 16,9-8 12/90

-16.9-9 12/90 16.9-10 12/90 16.9-11 12/90 16.9-12 12/90

-16.9-13 12/90 16.9-14 -12/90 16.9-15 12/90 116.9-16 12/90 16.9 12/90 i Table 16.9-3 1 of 5-

- 12/90 Table 16.9-3 2 of 5 12/90 Table 16.9-3 3-of 5 12/90

-Table 16.9-3 4 of 5 12/90-Table 16.9-3 5 of 5 12/90 Tab 16.10 l 16 .10-1~.- 2/91 L .16.10-2 '2/91 t-

-Tab-16.11

! Tab 16._1_22

Tab 16.13 16.13-0 12/90 l

16.13-1 12/90 Page 2 2/91

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-i 16.10 STEAM AMD POWER CONVERSION SYSTEM  !

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STEAM VENT TO ATMOSPHERE ,

16.10-1 l

COMMITMENT l l

Three steam generator PORV safety-related gas supply system l shall be OPERABLE with both nitrogen bottles per S/G PORV pressurized to greater than or equal to 2100 psig.

-t I

APPLICABILITY-Modes 1, 2, 3, and 4*

REMEDIAL ACTION: ,

a. With one nitrogen bottle on one or more S/G's less than'2100 psig, immediately start corrective action to' return the nitrogen supply to OPERABLE. i 1

Work to return the nitrogen supply to OPERABLE status 7"'s should continue without interruption.

L

b. .With two nitrogen bottles on one or more S/G's less than 2100 psig consider the PORVls) inoperable and  ;

refer to Technical Specification 3.7.1.6 for the  !

required ACTION.

TESTING REQUIREMENTS:

a. At least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-by verifying that both- l

. nitrogen bottles per S/G PORV has a pressure greater than or equal to 2100-psig.

REFERENCES:

-i

1) Design Basis Specification for the Catawba Main Steam, Main Steam Vent to Atmosphere and Main Steam Bypass to Condenser System,.Section 20.3.4

2) PIR 0-C90-0304

3) Branch Technical Position RSBS-1 r~g 4) CNC-1223.43-01-0011, rev. 1 5'"'/

• When Steam Generators are being used for decay heat removal.

16.10-1 2/91

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!:: i L a l BASESi1 l l -; .. .

i Design Engineering. calculation-CNC-1223.43-01-0011,;rev 1 d

demonstrates that.with~one nitrogen bottle charged to at i least 2100 psig,_ sufficient nitrogen exists to meet-the Tech-Spec: Design Bases;of the S/G'PORV's.

!:I -A revision to: calculation CNC-1223.43 : 1 also

!' demonstrates =that with two nitrcgen.bottli charged to at l  :-least 2100 psig, sufficient nitrogen exists to meet the 4 I

Branch Technical-Position RSB5-1 of supporting a controlled cooldown to the point where residual heat removal system can beLput into service with or without offsite power-following an earthquake.

p :The' COMMITMENT 1for having both nitrogen: bottles pressurized H to greater than or equal to 2100 psig and the REMEDIAL' l g . ACTION is adequate to ensure the intent of our FSAR i

. commitment to Branch Technical Position RSBS-1 is met.

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