ML022740503

Technical Specifications Bases Revision 19 Update

ML022740503
Person / Time
Site:	Palo Verde
Issue date:	09/26/2002
From:	Bauer S Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-04843-/SAB/TNW/DWG
Download: ML022740503 (19)

Text

LAM Scott A. Bauer Department Leader Regulatory Affairs Tel 623/393-5978 Mail Station 7636 Palo Verde Nuclear Fax 623/393-5442 P 0 Box 52034 Generating Station e-mail sbauer@apsc com Phoenix, AZ 85072-2034 102-04843-/SAB/TNW/DWG September 26, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, and 3 Docket Nos. STN 50-528/5291530 Technical Specifications Bases Revision 19 Update Pursuant to PVNGS Technical Specification (TS) 5.5.14, "Technical Specifications Bases Control Program," Arizona Public Service Company (APS) is submitting changes to the TS Bases incorporated into Revision 19, implemented on September 20, 2002.

The Revision 19 insertion instructions and replacement pages are provided in the Enclosure.

No commitments are being made to the NRC by this letter.

Should you have any questions, please contact Thomas N. Weber at (623) 393-5764.

Sincerely, J4140 44ýý SAB/TNW/DWG/kg

Enclosure:

PVNGS Technical Specification Bases Revision 19 Insertion Instructions and Replacement Pages cc: E. W. Merschoff J. N. Donohew N. L. Salgado

,0lO A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway o Comanche Peak

• Diablo Canyon 0 Palo Verde 0 South Texas Project o Wolf Creek

ENCLOSURE PVNGS Technical Specification Bases Revision 19 Insertion Instructions and Replacement Pages

Remove Page: Insert New Page:

Cover page Cover page List of Effective Pages, List of Effective Pages, Pages 1/2 through Pages 1/2 through List of Effective Pages, List of Effective Pages, Page 7/blank Page 7/blank B 3.3.11-5/B 3.3.11-6 B 3.3.11-5/B 3.3.11-6 B 3.9.3-1/B 3.9.3-2 B 3.9.3-1/B 3.9.3-2 B 3.9.3-3/B 3.9.3-4 B 3.9.3-3/B 3.9.3-4 B 3.9.3-5/B 3.9.3-6 B 3.9.3-5/B 3.9.3-6

PVNGS Palo Verde Nuclear GeneratingStation Units 1, 2, and 3 Spf Technical pecification Bases Revision 19 September 20, 2002 t i

-TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev. Page Rev No. No. No. No.

B 2.1.1-1 0 B 3.1.4-5 0 B 2.1.1-2 0 B 3.1.5-1 0 "B 2.1.1-3 10 B 3.1.5-2 12 "B 2.1.1-4 0 B 3.1.5-3 0 B 2.1.1-5 0 B 3.1.5-4 0 B 2.1.2-1 0 B 3.1.5-5 7 B 2.1.2-2 0 B 3.1.5-6 0 B 2.1.2-3 0 B 3.1.5-7 1 B 2.1.2-4 0 B 3.1.5-8 1 B 2.1.2-5 0 B 3.1.5-9 0 B 3.0-1 0 B 3.1.5-10 5 B 3.0-2 0 B 3.1.5-11 12 B 3.0-3 0 B 3.1.6-1 0 B 3.0-4 0 B 3.1.6-2 0 B 3.0-5 0 B 3.1.6-3 0 B 3.0-6 1 B 3.1.6-4 0 B 3.0-7 0 B 3.1.7-1 0 B 3.0-8 0 B 3.1.7-2 0 B 3.0-9 0 B 3.1.7-3 0 B 3.0-10 14 B 3.1.7-4 0 B 3.0-11 14 B 3.1.7-5 0 B 3.0-12 14 B 3.1.7-6 0 B 3.0-13 0 B 3.1.7-7 0 B 3.0-14 0 B 3.1.7-8 0 B 3.0-15 0 B 3.1.7-9 0 B 3.0-16 17 B 3.1.8-1 0 B 3.0-17 17 B 3.1.8-2 0 B 3.0-18 17 B 3.1.8-3 0 B 3.0-19 17 B 3.1.8-4 0 B 3.1.1-1 0 B 3.1.8-5 0 B 3.1.1-2 0 B 3.1.9-1 0 "B 3.1.1-3 12 B 3.1.9-2 0 "B 3.1.1-4 12 B 3.1.9-3 0 "B 3.1.1-5 12 B 3.1.9-4 0 B 3.1.1-6 0 B 3.1.9-5 7 B 3.1.2-1 0 B 3.1.9-6 1 B 3.1.2-2 0 B 3.1.10-1 0 B 3.1.2-3 5 B 3.1.10-2 0 B 3.1.2-4 12 B 3.1.10-3 0 B 3.1.2-5 0 B 3.1.10-4 0 B 3.1.2-6 0 B 3.1.10-5 0 B 3.1.2-7 12 B 3.1.10-6 0 B 3.1.2-8 0 B 3.1.11-1 0 B 3.1.2-9 0 B 3.1.11-2 0 B 3.1.3-1 0 B 3.1.11-3 0 "B3.1.3-2 0 B 3.1.11-4 0 "B3.1.3-3 0 B 3.1.11-5 0 "B3.1.3-4 0 B 3.2.1-1 0 "B 3.1.3-5 0 B 3.2.1-2 10 "B 3.1.3-6 0 B 3.2.1-3 0 B 3.1.4-1 0 B 3.2.1-4 0 "B 3.1.4-2 0 B 3.2.1-5 0 "B 3.1.4-3 0 B 3.2.1-6 0 "B 3.1.4-4 0 B 3.2.1-7 0 PALO VERDE UNITS 1, 2, AND 3 1 Revision 19 September 20, 2002

TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev. Page Rev No. No. No. No.

3.2.1-8 0 B 3.3.1-21 15 3.2.2-1 0 B 3.3.1-22 15 3.2.2-2 10 B 3.3.1-23 15 3.2.2-3 0 B 3.3.1-24 15 3.2.2-4 0 B 3.3.1-25 15 3.2.2-5 1 B 3.3.1-26 15 3.2.2-6 0 B 3.3.1-27 15 3.2.2-7 0 B 3.3.1-28 15 3.2.3-1 0 B 3.3.1-29 15 3.2.3-2 10 B 3.3.1-30 15 3.2.3-3 0 B 3.3.1-31 15 3.2.3-4 0 B 3.3.1-32 15 3.2.3-5 0 B 3.3.1-33 15 3.2.3-6 0 B 3.3.1-34 15 3.2.3-7 0 B 3.3.1-35 15 3.2.3-8 0 B 3.3.1-36 15 3.2.3-9 0 B 3.3.1-37 15 3.2.3-10 0 B 3.3.1-38 15 3.2.4-1 0 B 3.3.1-39 15 3.2.4-2 10 B 3.3.1-40 15 3.2.4-3 0 B 3.3.1-41 15 3.2.4-4 0 B 3.3.1-42 15 3.2.4-5 0 B 3.3.1-43 15 3.2.4-6 0 B 3.3.2-1 0 3.2.4-7 0 B 3.3.2-2 0 3.2.4-8 0 B 3.3.2-3 1 3.2.4-9 0 B 3.3.2-4 1 3.2.5-1 0 B 3.3.2-5 0 3.2.5-2 10 B 3.3.2-6 15 3.2.5-3 0 B 3.3.2-7 15 3.2.5-4 0 B 3.3.2-8 15 3.2.5-5 0 B 3.3.2-9 15 3.2.5-6 0 B 3.3.2-10 15 3.2.5-7 0 B 3.3.2-11 15 3 .3.1-1 0 B 3.3.2-12 15 3 .3.1-2 0 B 3.3.2-13 15 3 .3.1-3 0 B 3.3.2-14 15 3.3.1-4 0 B 3.3.2-15 15 3.3.1-5 18 B 3.3.2-16 15 3.3.1-6 0 B 3.3.2-17 15 3.3.1-7 0 B 3.3.3-1 0 3.3.1-8 0 B 3.3.3-2 18 3.3.1-9 15 B 3.3.3-3 0 3.3.1-10 0 B 3.3.3-4 0 3 .3 .1-11 0 B 3.3.3-5 7 3.3.1-12 1 B 3.3.3-6 0 3 .3 .1-13 1 B 3.3.3-7 0 3.3.1-14 0 B 3.3.3-8 0 3.3.1-15 6 B 3.3.3-9 0 3.3.1-16 0 B 3.3.3-10 0 3.3.1-17 0 B 3.3.3-11 0 3.3.1-18 0 B 3.3.4-1 0 3.3.1-19 15 B 3.3.4-2 0 3.3.1-20 15 B 3.3.4-3 0 PALO VERDE UNITS 1, 2, AND 3 2 Revision 19 September 20, 2002

TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev. Page Rev No. No. No. No.

3.3.4-4 0 3.3.6-14 0 3.3.4-5 0 3.3.6-15 0 3.3.4-6 0 3.3.6-16 0 3.3.4-7 0 3.3.6-17 0 3.3.4-8 0 3.3.6-18 0 3.3.4-9 0 3.3.6-19 0 3.3.4-10 0 3.3.6-20 0 3.3.4-11 0 3.3.6-21 3.3.4-12 0 3.3.6-22 3.3.4-13 0 3.3.7-1 2 3.3.4-14 0 3.3.7-2 2 3.3.4-15 0 3.3.7-3 0 3.3.5-1 0 3.3.7-4 0 3.3.5-2 0 3.3.7-5 0 3.3.5-3 0 3.3.7-6 0 3.3.5-4 0 3.3.7-7 0 3.3.5-5 0 3.3.7-8 0 3.3.5-6 0 3.3.7-9 2 3.3.5-7 0 3.3.8-1 0 3.3.5-8 0 3.3.8-2 0 3.3.5-9 0 3.3.8-3 0 3.3.5-10 0 3.3.8-4 0 3.3.5-11 0 3.3.8-5 0 3.3.5-12 1 3.3.8-6 1 3.3.5-13 0 3.3.8-7 0 3.3.5-14 0 3.3.8-8 0 3.3.5-15 0 3.3.9-1 0 3.3.5-16 0 3.3.9-2 2 3.3.5-17 0 3.3.9-3 0 3.3.5-18 0 3.3.9-4 10 3.3.5-19 0 3.3.9-5 1 3.3.5-20 1 3.3.9-6 0 3.3.5-21 0 3.3.9-7 0 3.3.5-22 0 3.3.10-1 0 3.3.5-23 0 3.3.10-2 0 3.3.5-24 0 3.3.10-3 0 3.3.5-25 0 3.3.10-4 0 3.3.5-26 0 3.3.10-5 18 3.3.5-27 10 3.3.10-6 0 3.3.5-28 10 3.3.10-7 0 3.3.5-29 10 3.3.10-8 14 3.3.6-1 0 3.3.10-9 14 3.3.6-2 0 3.3.10-10 14 3.3.6-3 0 3.3.10-11 14 3.3.6-4 0 3.3.10-12 14 3.3.6-5 0 3.3.10-13 14 3.3.6-6 0 3.3.10-14 14 3.3.6-7 0 3.3.10-15 14 3.3.6-8 0 3.3.10-16 14 3.3.6-9 0 3.3.10-17 14 3.3.6-10 0 3.3.10-18 14 3.3.6-11 0 3.3.10-19 14 3.3.6-12 0 3.3.10-20 14 3.3.6-13 0 3.3.10-21 14 PALO VERDE :UNITS 1. 2, AND 3 3 Revision 19 September 20, 2002

TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev. Page Rev No. No. No. No.

3.3 .11-1 0 3.4.9-3 1 3.3 .11-2 2 3.4.9-4 0 3.3 .11-3 2 3.4.9-5 0 3.3 .11-4 2 3.4.9-6 0 3.3.11-5 19 3 .4.10-1 0 3.3.11-6 2 3 .4.10-2 7 3.3.11-7 2 3.4.10-3 0 3.3.12-1 15 3 .4.10-4 0 3.3.12-2 15 3 .4.11-1 0 3.3.12-3 5 3.4.11-2 7 3.3.12-4 5 3.4.11-3 0 3.3.12-5 6 3.4.11-4 0 3.3.12-6 6 3 .4.11-5 0 3.4.1-1 10 3 .4.11-6 0 3.4.1-2 7 3.4.12-1 1 3.4.1-3 0 3.4.12-2 1 3.4.1-4 0 3 .4.12-3 0 3.4.1-5 0 3.4.12-4 0 3.4.2-1 7 3.4.12-5 0 3.4.2-2 1 3.4.13-1 0 3.4.3-1 0 3 .4.13-2 0 3.4.3-2 0 3 .4.13-3 1 3.4.3-3 0 3.4.13-4 0 3.4.3-4 2 3.4.13-5 0 3.4.3-5 2 3.4.13-6 0 3.4.3-6 0 3.4.13-7 2 3.4.3-7 0 3.4.13-8 2 3.4.3-8 2 3.4.13-9 0 3.4.4-1 0 3.4.13-10 2 3.4.4-2 7 3.4.14-1 0 3.4.4-3 7 3.4.14-2 2 3 .4.4-4 0 3.4.14-3 2 3.4.5-1 0 3.4.14-4 7 3.4.5-2 6 3.4.14-5 2 3.4.5-3 6 3.4.14-6 2 3.4.5-4 0 3.4.14-7 2 3.4.5-5 6 3.4.15-1 0 3.4.6-1 0 3.4.15-2 0 3.4.6-2 6 3.4.15-3 0 3.4.6-3 6 3.4.15-4 0 3.4.6-4 6 3.4.15-5 0 3.4.6-5 6 3.4.15-6 0 3.4.7-1 0 3.4.15-7 0 3.4.7-2 6 3.4.16-1 2 3.4.7-3 6 3.4.16-2 10 3.4.7-4 2 3.4.16-3 0 3.4.7-5 0 3.4.16-4 0 3.4.7-6 0 3.4.16-5 0 3.4.7-7 6 3.4.16-6 0 3.4.8-1 0 3.4.17-1 0 3.4.8-2 6 3.4.17-2 0 3.4.8-3 6 3.4.17-3 0 3.4.9-1 0 3.4.17-4 0 3.4.9-2 0 3.4.17-5 0 PALO VERDE UNITS 1, 2, AND 3 4 Revision 19 September 20, 2002

TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev. Page Rev No. No. No. No.

3.4.17-6 0 3.6.2-4 0 3.5.1-1 0 3.6.2-5 0 3.5.1-2 0 3.6.2-6 0 3.5.1-3 7 3.6.2-7 0 3.5.1-4 0 3.6.2-8 0 3.5.1-5 0 3.6.3-1 0 3.5.1-6 0 3.6.3-2 0 3.5.1-7 1 3.6.3-3 0 3.5.1-8 1 3.6.3-4 1 3.5.1-9 0 3.6.3-5 1 3.5.1-10 1 3.6.3-6 1 3.5.2-1 0 3.6.3-7 1 3.5.2-2 0 3.6.3-8 11 3.5.2-3 0 3.6.3-9 1 3.5.2-4 0 3.6.3-10 11 3.5.2-5 0 3.6.3-11 11 3.5.2-6 0 3.6.3-12 11 3.5.2-7 1 3.6.3-13 1 3.5.2-8 1 3.6.3-14 1 3.5.2-9 1 3.6.3-15 1 3.5.2-10 1 3.6.3-16 1 3.5.3-1 0 3.6.3-17 1 3.5.3-2 3.6.4-1 0 3.5.3-3 3.6.4-2 1 3.5.3-4 0 3.6.4-3 1 3.5.3-5 0 3.6.5-1 0 3.5.3-6 3.6.5-2 1 3.5.3-7 2 3.6.5-3 0 3.5.3-8 10 3.6.5-4 0 3.5.3-9 0 3.6.6-1 0 3.5.3-10 2 3.6.6-2 3.5.4-1 2 3.6.6-3 1 3.5.4-2 3.6.6-4 7 3.5.4-3 3.6.6-5 1 3.5.5-1 0 3.6.6-6 0 3.5.5-2 7 3.6.6-7 1 3.5.5-3 415 0 3.6.6-8 1 3.6.6-9 0 0

3.5.5-4 40 3.5.5-5 0 3.6.7-1 0 3.5.5-6 0 3.6.7-2 0 3.5.5-7 0 3.6.7-3 0 3.5.6-1 0 3.6.7-4 0 3.5.6-2 1 3.6.7-5 0 3.5.6-3 0 3.7.1-1 7 3.5.6-4 1 3.7.1-2 7 3.5.6-5 0 3.7.1-3 0 3.6.1-1 0 3.7.1-4 0 3.6.1-2 0 3.7.1-5 1 3.6.1-3 0 3.7.1-6 7 3.6.1-4 0 3.7.2-1 0 3.6.1-5 0 3.7.2-2 0 3.6.2-1 0 3.7.2-3 0 3.6.2-2 6 3.7.2-4 0 3.6.2-3 0 3.7.2-5 0 PALO VERDE UNITS 1, 2, AND 3 5 Revision 19 September 20, 2002

TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev. Page Rev No. No. No. No.

"B3.7.2-6 0 "B3.7.13-4 0 "B37.3-1 1 "B3.7.13-5 0 "B3.7.3-2 1 "B3.7.14-1 0 "B3.7.3-3 1 "B3.7.14-2 0 "B3.7.3-4 0 "B3.7.14-3 0 "B3.7.3-5 0 "B3.7.15-1 3 "B3.7.4-1 0 "B3.7.15-2 3 "B3.7.4-2 0 "B3.7.16-1 7 "B3.7.4-3 0 "B3.7.16-2 0 "B3.7.4-4 0 "B3.7.16-3 0 "B3.7.5-1 0 "B3.7.16-4 0 "B3.7.5-2 "B3.7.17-1 3 "B3.7.5-3 "B3.7.17-2 3 "B3.7.5-4 0 0

"B3.7.17-3 3 "B3.7.5-5 9 "B3.7.17-4 3 "B3.7.5-6 9 "B3.7.17-5 3 "B3.7.5-7 9 "B3.7.17-6 3 "B3.7.5-8 9 B 3.8.1-1 0 "B3.7.5-9 9 "B3.8.1-2 2 "B3.7.5-10 "B3.8.1-3 13 B.3.7.5-11 "B3.8.1-4 2 B 3.7.6-1 0 "B3.8.1-5 2 B 3.7.6-2 0 "B3.8.1-6 2 B 3.7.6-3 5 "B3.8.1-7 2 B 3.7.6-4 0 "B3.8.1-8 2 B 3.7.7-1 0 "B3.8.1-9 2 B 3.7.7-2 1 "B3.8.1-10 2 B 3.7.7-3 1 B 3.8.1-11 2 B 3.7.7-4 1 "B3.8.1-12 2 B 3.7.7-5 1 "B3.8.1-13 2 B 3.7.8-1 1 "B3.8.1-14 2 B 3.7.8-2 1 "B3.8.1-15 2 B 3.7.8-3 1 "B3.8.1-16 2 B 3.7.8-4 1 "B3.8.1-17 2 B 3.7.9-1 0 B 3.8.1-18 2 B 3.7.9-2 1 "B3.8.1-19 13 B 3.7.9-3 0 "B3.8.1-20 13 B 3.7.10-1 10 "B3.8.1-21 13 B 3.7.10-2 1 "B3.8.1-22 13 B 3.7.10-3 1 "B3.8.1-23 6 B 3.7.10-4 1 "B3.8.1-24 6 B 3.7.11-1 0 B 3.8.1-25 6 B 3.7.11-2 0 B 3.8.1-26 6 B 3.7.11-3 1 B 3.8.1-27 6 B 3.7.11-4 10 B 3.8.1-28 6 B 3.7.11-5 10 B 3.8.1-29 6 B 3.7.11-6 10 B 3.8.1-30 6 B 3.7.12-1 1 B 3.8.1-31 6 B 3.7.12-2 1 B 3.8.1-32 6 B 3.7.12-3 10 B 3.8.1-33 6 B 3.7.12-4 10 B 3.8.1-34 6 B 3.7.13-1 0 B 3.8.1-35 6 B 3.7.13-2 0 B 3.8.1-36 6 B 3.7.13-3 0 B 3.8.1-37 6 PALO VERDE UNITS 1, 2, AND 3 6 Revision 19 September 20, 2002

TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev. Page Rev No. No. No. No.

B 3.8.1-38 B 3.8.9-3 0 B 3.8.1-39 B 3.8.9-4 0 B 3.8.1-40 B 3.8.9-5 0 B 3.8.1-41 B 3.8.9-6 0 B 3.8.2-1 B 3.8.9-7 0 B 3.8.2-2 B 3.8.9-8 0 B 3.8.2-3 B 3.8.9-9 0 B 3.8.2-4 B 3.8.9-10 0 B 3.8.2-5 B 3.8.9-11 0 B 3.8.2-6 B 3.8.10-1 0 B 3.8.3-1 B 3.8.10-2 0 B 3.8.3-2 B 3.8.10-3 0 B 3.8.3-3 B 3.8.10-4 0 B 3.8.3-4 B 3.9.1-1 0 B 3.8.3-5 B 3.9.1-2 0 B 3.8.3-6 B 3.9.1-3 0 B 3.8.3-7 B 3.9.1-4 0 B 3.8.3-8 B 3.9.2-1 15 B 3.8.3-9 B 3.9.2-2 15 B 3.8.4-1 B 3.9.2-3 15 B 3.8.4-2 B 3.9.2-4 15 B 3.8.4-3 B 3.9.3-1 18 B 3.8.4-4 B 3.9.3-2 19 B 3.8.4-5 B 3.9.3-3 19 B 3.8.4-6 B 3.9.3-4 19 B 3.8.4-7 B 3.9.3-5 19 B 3.8.4-8 B.3.9.3-6 19 B 3.8.4-9 B 3.9.4-1 0 B 3.8.4-10 B 3.9.4-2 1 B 3.8.4-11 B 3.9.4-3 0 B 3.8.5-1 B 3.9.4-4 0 B 3.8.5-2 B 3.9.5-1 0 B 3.8.5-3 B 3.9.5-2 16 B 3.8.5-4 B 3.9.5-3 16 B 3.8.5-5 B 3.9.5-4 16 B 3.8.5-6 B.3.9.5-5 16 B 3.8.6-1 "B3.9.6-1 0 B 3.8.6-2 "B 3.9.6-2 0 B 3.8.6-3 "B 3.9.6-3 0 B 3.8.6-4 "B 3.9.7-1 0 B 3.8.6-5 "B 3.9.7-2 0 B 3.8.6-6 "B 3.9.7-3 0 B 3.8.6-7 B 3.8.7-1 B 3.8.7-2 B 3.8.7-3 B 3.8.7-4 B 3.8.8-1 B 3.8.8-2 B 3.8.8-3 B 3.8.8-4 B 3.8.8-5 B 3.8.9-1 B 3.8.9-2 PALO VERDE UNITS 1, 2, AND 3 7 Revision 19 September 20, 2002

Remote Shutdown System B 3.3.11 BASES ACTIONS A Remote Shutdown System division is inoperable when each (continued) Function listed in Table 3.3.11-1 is not accomplished by the required number of channels in Table 3.3.11-1 that satisfies the OPERABILITY criteria for the channel's Function. These criteria are outlined in the LCO section of the Bases.

Note 2 has been added in the ACTIONS to'clarify the application of Completion Time rules. The Conditions of this Specification may be entered independently for each Function listed in Table 3.3.11-1. The Completion Time(s) of the inoperable channel(s)/train(s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function.

A.1 Condition A addresses the situation where one or more instrumentation channels of the Remote Shutdown System are inoperable. This includes any Function listed in Table 3.3.11-1.

The Required Action is to restore the channels to OPERABLE status within 30 days. The Completion Time is based on operating experience and the low probability of an event th at would require evacuation of the control room.

B.1 and B.2 Condition B addresses the situation where one or more disconnect or control circuits of the Remote Shutdown System are inoperable. The required disconnect and control circuits are listed in PVNGS controlled documents.

The required Action is to restore the required switch(s)/circuit(s) to OPERABLE status or issue procedure changes that identify alternate disconnect methods or control circuits. The Completion Time for either of the two Actions is 30 days.

(continued)

PALO VERDE UNITS 1,2.3 B 3.3.11-5 REVISION 19

Remote Shutdown System B 3.3.11 BASES ACTIONS C.1 and C.2 (continued)

If the Required Action and associated Completion Time of Condition A are not met, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status.

the plant must be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required MODE from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.3.11.1 REQUIREMENTS Performance of the CHANNEL CHECK once every 31 days ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or of something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying that the instrumentation continues to operate properly between each CHANNEL CALIBRATION. Agreement criteria are determined by the plant staff, based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the sensor or the signal processing equipment has drifted outside its limit. As specified in the Surveillance, a CHANNEL CHECK is only required for those channels that are normally energized.

If the channels are normally off scale during times when surveillance is required, the CHANNEL CHECK will only verify that they are offscale in the same direction. Current loop channels are verified to be reading at the bottom of the range and not failed downscale.

The Frequency of 31 days is based on plant operating experience with regard to channel OPERABILITY and drift, which demonstrates that failure of more than one channel of a given Function in any 31 day interval is a rare event.

(continued)

PALO VERDE UNITS 1,2,3 B 3.3.11-6 REVISION 2

Containment Penetrations B 3.9.3 B 3.9 REFUELING OPERATIONS B 3.9.3 Containment Penbtrations BASES BACKGROUND During CORE ALTERATIONS or movement of fuel assemblies within containment with irradiated fuel in containment, a release of fission product radioactivity within the containment will be restricted from escaping to the environment when the LCO requirements are met. In MODES 1, 2, 3, and 4, this is accomplished by maintaining containment OPERABLE as described in LCO 3.6.1, "Containment." In MODE 6, the potential for containment pressurization as a result of an accident is not likely; therefore, requirements to isolate the containment from the outside atmosphere can be less stringent. The LCO requirements are referred to as "containment closure" rather than "containment OPERABILITY."

Containment closure means that all potential escape paths are closed or capable of being closed. Since there is no Yotential for containment pressurization, the Appendix J eakage criteria and tests are not required.

The containment serves to contain fission product radioactivity that may be released from the reactor core following an accident, such that offsite radiation exposures are maintained well within the requirements of 10 CFR 100.

Additionally, the containment structure provides radiation shielding from the fission products that may be present in the containment atmosphere following accident conditions.

The containment equipment hatch, which is part of the containment pressure boundary, providesý a means for moving large equipment and components into and out of containment.

During CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, the equipment hatch must be capable of being closed and held in place by at least four I bolts. Good engineering practice dictates that the bolts required by this LCO be approximately equally spaced.

The containment air locks, which are also part of the containment pressure boundary, provide a means for personnel access during MODES 1, 2. 3, and 4 operation in accordance with LCO 3.6.2, "Containment Air Locks." Each air lock has doors at both ends. The doors are normally interlocked to prevent simultaneous opening when containment OPERABILITY is required. During periods of shutdown when containment (continued)

PALO VERDE UNITS 1,2,3 B 3.9.3-1 REVISION 18

Containment Penetrations B 3 9.3 BASES BACKGROUND closure is not required, the door interlock mechanism may be (continued) disabled, allowing both doors of an air lock to remain open for extended periods when frequent containment entry is necessary. During CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, containment closure is required: therefore, the door interlock mechanism may remain disabled, but one air lock door must always remain capable of being closed.

The requirements on containment penetration closure ensure that a release of fission product radioactivity within containment will be restricted to within regulatory limits.

I The Containment Purge and Exhaust System includes two subsystems. The refueling purge subsystem includes a 42 inch supply penetration and a 42 inch exhaust penetration. The second subsystem, power access purge subsystem, includes an 8 inch supply penetration and an 8 inch exhaust penetration. During MODES 1, 2, 3. and 4, the two valves in each of the refueling purge supply and exhaust penetrations are secured in the closed position.

The two valves in each of the two power access purge penetrations can be opened intermittently, but are closed automatically by the Engineered Safety Features Actuation System (ESFAS). Neither of the subsystems is subject to a Specification in MODE 5.

In MODE 6. large air exchanges are necessary to conduct refueling operations. The refueling purge system is used for this purpose and the valves are closed by the ESFAS in accordance with LCO 3.3.8, "Containment Purge Isolation Actuation Signal (CPIAS)."

The Power Access Purge System remains operational in MODE 6 and the valves are also closed by the ESFAS.

The other containment penetrations that provide direct access from containment atmosphere to outside atmosphere must be isolated on at least one side. Isolation may be achieved by an OPERABLE automatic isolation valve, or by a manual isolation valve, blind flange, or equivalent.

(continued)

PALO VERDE UNITS 1,2,3 B 3.9.3-2 REVISION 19

Containment Penetrations B 3.9.3 BASES BACKGROUND Equivalent isolation'methods must'be approved and may (continued) include use of devices designed to allow eddy current testing and sludge lancing of the steam generators. Devices which present a substantial restriction to the release of containment atmosphere may be considered equivalent.

APPLICABLE During CORE ALTERATIONS or movement of irradiated fuel SAFETY ANALYSES assemblies within containment, the most severe radiological consequences result from a fuel handling accident. The fuel handling accident is a-postulated event-that involves damage to irradiated fuel (Ref. 2). Fuel handling accidents, analyzed in Reference 2, include dropping a single irradiated fuel assembly and handling tool or a heavy object onto other irradiated fuel assemblies. The requirements of LCO 3.9.6. "Refueling Water Level-Fuel Assemblies," LCO 3.9.7. "Refueling Water-Level-CEAs," and the minimum decay time of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to CORE ALTERATIONS ensure that the release of fission product radioactivity, subsequent to a fuel handling accident, results in doses that are well within the guideline values specified in 10 CFR 100. The acceptance limits for offsite radiation exposure are contained in Standard Review Plan Section 15.7.4, Rev. 1 (Ref. 3), which defines "well within" 10 CFR 100 to be 25%

or less of the 10 CFR-100 values.

Containment penetrations satisfy Criterion 3 of 10 CFR 50.36 (c)(2)(ii).

LCO This LCO limits the consequences of a-fuel handling accident in containment by limiting the potential escape paths for fission product radioactivity released within containment.

The LCO requires any penetration providing direct access from the containment atmosphere to the outside atmosphere to be closed except for the OPERABLE containment purge supply exhaust penetrations, containment personnel airlocks, and equipment hatch. For the OPERABLE containment purge supply and exhaust penetrations, this LCO ensures that these "

I cxpenetrations are isolable by a valve in the Containment Purge Isolation-System. The OPERABILITY requirements for this LCO ensure that~the automatic-purge valve closure times specified in the UFSAR can be achieved and therefore meet the assumptions used in the safety analysis to ensure releases through the valves are terminated, such that the radiological doses are within the acceptance limit. The

• (continued)

PALO VERDE UNITS 1,2,3 B 3.9.3-3 REVISION 19

Containment Penetrations B 3.9.3 BAS ES LCO equipment hatch is required to be kept free of obstructions (continued) that could impede its closure so it is capable of being closed with a minimum of four bolts should a fuel handling accident occur inside containment.

The containment personnel airlock doors may be open during movement of irradiated fuel in the containment and during CORE ALTERATIONS provided that one door is capable of being closed in the event of a fuel handling accident. Should a fuel handling accident occur inside containment, one personnel airlock door will be closed following an evacuation of containment.

The LCO is modified by a Note allowing penetration flow paths with direct access from the containment atmosphere to the outside atmosphere to be unisolated under administrative controls. Administrative controls ensure that 1) appropriate personnel are aware of the open status of the penetration flow path during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, and 2) specified individuals are designated and readily available to isolate the flow path in the event of a fuel handling accident.

APPLICABILITY The containment penetration requirements are applicable during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment because this is when there is a potential for a fuel handling accident. In MODES 1, 2, 3, and 4, containment penetration requirements are addressed by LCO 3.6.1, "Containment." In MODES 5 and 6, when CORE ALTERATIONS or movement of irradiated fuel assemblies within containment are not being conducted, the potential for a fuel handling accident does not exist. Therefore, under these conditions no requirements are placed on containment penetration status.

ACTIONS A.1 and A.2 With the containment equipment hatch, air locks, or any containment penetration that provides direct access from the containment atmosphere to the outside atmosphere not in the required status, including the Containment Purge Isolation System not capable of automatic actuation when the purge (continued)

PALO VERDE UNITS 1,2,3 B 3.9.3-4 REVISION 19

Containment Penetrations B 3.9.3 BASES ACTIONS A.1 and A.2 (continued) valves are open, the unit must be~placed in a condition in which the isolation function is not needed. This is

.accomplished by~immediately suspending CORE ALTERATIONS and movement of irradiated fuel assemblies within containment.

Performance of these actions shall not preclude completion of movement of a component to a safe position.

SURVEILLANCE SR 3.9.3.1 REQUIREMENTS This Surveillancedemnonstrates that each of the containment penetrations required to be in its-'closed position is in that position.-The Surveillance on the open purge and "exhaust~valves will demonstrate that the valves are not blocked from closing. Also, the Surveillance will demonstrate that each valve operator has motive-power, which will ensure each valve is capable of being closed by an OPERABLE automatic containment purge isolation signal.

The Surveillance is performed every 7 days duringCORE ALTERATIONS or movement of irradiated fuel assemblies within the containment. The Surveillance-interval is selected to be commensurate with the normal duration of time to complete fuel handling operations.' A surveillance before the start of refueling operations will provide two or three surveillance Verifications durin-gthe-applidable-period for this LCO. As such, this Surveillance ensures that a postulated fuel handling accident that releases fission product radioactivity within the containment will not result in a release of fission product radioactivity to the environment in excess of those recommended by Standard Review Plan Section 15.7.4 (Reference 3).

SR 3.9.3.2 This Surveillance demonstrates that each containment purge valve actuates to its isolation position on manual initiation or on an actual or simulated high radiation signal. The 18 month Frequency maintains consistency with other similar ESFAS instrumentation and valve testing requirements. The CPIAS is tested in accordance with LCO 3.3.8. "Containment Purge Isolation Actuation Signal (CPIAS)." SR 3.6.3.5 demonstrates that the isolation time of each valve is in accordance with the Inservice Testing (continued)

PALO VERDE UNITS 1,2.3 B 3.9.3-5 REVISION 19

Containment Penetrations B 3.9.3 BASES SURVILLANCE SR 3.9.3.2 (continued)

REQUIREMENTS Program requirements. These surveillances performed during MODE 6 will ensure that the valves are capable of closing after a postulated fuel handling accident to limit a release of fission product radioactivity from the containment.

SR 3.9.3.3 This Surveillance demonstrates that the necessary hardware, tools, equipment and personnel are available to close the equipment hatch and that the equipment hatch is clear of obstructions that would impede its closure. The 7-day Frequency is commensurate with the normal duration of time to complete the fuel handling operations. The Surveillance is only required to be met for an open equipment hatch. If the hatch is closed, the capability to close the hatch is not required.

REFERENCES 1. GPU Nuclear Safety Evaluation SE-0002000-O01, Rev. 0.

May 20, 1988.

2. UFSAR, Section 15.7.4.

3. NUREG-0800, Section 15.7.4, Rev. 1, July 1981.

PALO VERDE UNITS 1,2,3 B 3.9.3-6 REVISION 19