ML20029A424

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Rev 3 to Selected Licensee Commitments Manual
ML20029A424
Person / Time
Site: Catawba  Duke Energy icon.png
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.

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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

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

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manual is meant to contain commitments and other station issues that oin we believe warrent higher control, but are not appropriate in the f!g M

k Technical Specifications (TS). Instead of being updated with the 9

annual FSAR Update, the SLC Manual will be updated as needed during

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EE Very truly ours, E

M.S. Tuckman r

JAR / jar Attachment-I l

Mr Stewart D. Ebneter xt:

Regional Administrator, Region 11

-U.S. Nuclear Regulatory Commission

.101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 I

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- Februaryc14',' 1991 0,

Subject:

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

Revision 3 dated 2/91

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

. manual.

. 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 Jr.,.. Technical System Manager o

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CATAWBA NUCLEAR STATION-DUKE POWER COMPANY

-SELECTED LICENSEE COMMITMENTS MANUAL LIST OF EFFECTIVE PAGES Page Revision Date L0EP 1 2/91 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 I,).

16.2-2 1/91 q_

16.2-3 Tab 16.3 Tab 16.4 Tab 16.5-

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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

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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

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-Tab-16.11

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Tab 16.13 16.13-0 12/90 l

16.13-1 12/90 Page 2 2/91

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16.10 STEAM AMD POWER CONVERSION SYSTEM 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.

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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.

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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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BASESi1 i

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d Design Engineering. calculation-CNC-1223.43-01-0011,;rev 1 demonstrates that.with~one nitrogen bottle charged to at least 2100 psig,_ sufficient nitrogen exists to meet-the Tech-Spec: Design Bases;of the S/G'PORV's.

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-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

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.

The' COMMITMENT 1for having both nitrogen: bottles pressurized p

to greater than or equal to 2100 psig and the REMEDIAL' H

. ACTION is adequate to ensure the intent of our FSAR i

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

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