ML18151A348

Forwards Rev 25 to Updated FSAR & Operational QA Program TR

ML18151A348
Person / Time
Site:	Surry
Issue date:	01/17/1996
From:	Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18151A349	List: ML18151A348 ML18151A435
References
NUDOCS 9601260048
Download: ML18151A348 (143)

Text

.I VIRGINIA ELECTRIC *AND POWER COMPANY RICHMOND, VIRGINIA 23261 January 17, 1996 United States Nuclear Regulatory Commission Serial No.96-003 Attention: Document Control Desk NL&P/GDM Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

. VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT REVISION 25*

• Pursuant to 10 CFR 50.71 (e), Virginia Electric and Power Company submits Revision 25 to the Updated Final Safety Analysis Report (UFSAR) for the Surry Power Station Units 1 and 2. This revision updates Chapter 17 of the UFSAR which contains the Operational Quality Assurance (QA) Program. The changes to the program description do not reduce the commitments contained therein.

Each revision package contains replacement instructions and Revision 25 pages, including overleafs. The Revision 25 pages replace the existing pages as described in the instructions. One signed original and ten additional copies of Revision 25 to the UFSAR are enclosed.

As a duly authorized officer of the Virginia Electric and Power Company, I hereby certify that the information given in the enclosed Revision 25 of the UFSAR accurately

• presents changes prepared pursuant to Commission requirements.

Very truly yours,

~P.~

James P. O'Hanlon Senior Vice President - Nucl~ar 9601260048 960117 PDR ADOCK 05000280 K . PDR Enclosures (Original Revision 25 and ten copies) 250060

cc: U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900

_Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station

COMMONWEALTH OF VIRGINIA )

)

COUNTY OF HENRICO )

The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by J. P. O'Hanlon, who is Senior Vice President -

Nuclear, of Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this /77! day of , 19~.

My Commission Expires:

k)-1*~ Notary Public (SEAL)

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... REVISION 24 10/95 SPS UFSAR LEP 1 L+ST OP EPPECT+YE PAGES

• VOLUME I Raviaion

1. 4-24

1. 4-25

1. 4-26

1. 4-27 4/91 12/94 7/8 7/ 2 13 23 Original Original Original TOC-i 22 1. 4-28 7. 82 TOC-ii 10 1.4-29 /82 Original TOC-iii Original 1. 4-3 0 7/82 Original TOC-iv 19 1.4-31 7/82 Original

1. 4-32 7/82 Original Chapter 1 1. 4-33 7/82 Original

1. 4-34 7/82 Original 1-i Original 1. 4-35 7/82 Original 1-ii Original 1.4-36 10/95 24 1-iii Original 1. 4-37 7/82 Original 1-iv Original 1. 4-38 7/82 Original 1-v Original 1.4- 7/82 Original 1-vi Original 1.4 ~o 12/94 23 1.1-1 Original 1. -41 7/82 Original 1.1-2 24 1 4-42 7 /82 Original 1.1-3 24 .4-43 7/82 Original 1.1-4 24 1. 4-44 7/82 Original 1.2-1 1. 4-45 7/82 Original 1.2-2 1. 4-46 7/82 Original 1.2-3 1.4-47 7/82 Original 1.2-4 1.4-48 8/90 10

• 1.2-5 1. 4-49 7/82 Original 1.3-1 1. 4-50 12/91 15 1.3-2 1. 4-51 12/91 15 1.3-3 1.5-1 7/82 Original 1.3-4 1.5-2 12/91 15 1.3-5 1.6-1 10/95 24 1.3-6 1.6-2 7/82 Original 1.3-7 1.6-3 7/82 Original 1.3-8 1.6-4 7/82 Original 1.3-9 .6-5 7/82 Original

1. 3-10 6-6 7/82 Original

1. 4-1 1. 6-7 7/82 Original 1.4-2 1. -8 7/82 Original 1.4-3 Original 1. 6 7/82 Original 1.4-4 Original 1. 6- 0 7/82 Original 1.4-5 Original 1. 6-1 7/82 Original 1.4-6 13 1. 6-12 7/82 Original 1.4-7 Original 1.4-8 Original Chapter 1.4-9 Original 1.4-10 Original 2-i 4/94 22 1.4-11 Original 2-ii 6/83 1

1. 4-12 Original 2-iii 6/83 1 1.4-13 Original 2-iv 6/83 1

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1. 4-20 Original 2.1-1 22 1.4-21 Original 2.1-2 22 1.4-22 13 2.1-3 22 22

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REVISION 24 10/95 SPS UFSAR LEP-2

• LIST OP EPPECTIYE PAGES

.P.Jua.

VOLUME I 2.1-5 2.1-6 J2.ll.Jt (continued) 4/94 4/94 Raviaion 22 22 R..Lsul 2.2-19 2.2-20 2.2-21 2.2-22 l2.A.U.

8/93 8/93 8/93 8/93 Reviaion 20 20 20 20 2.1-7 4/94 22 2.2-23 8/93 20 2.1-8 4/94 22 Figure 2.2-1 8/93 20 2.1-9 4/94 22 Figure 2.2-2 8/93 20 2.1-10 4/94 22 Figure 2.2-3 8/93 20 2 .1-11 4/94 22 Figure 2.2-4 8/93 20 2.1-12 4/94 22 Figure 2.2-5 8/93 20 2 .1-13 4/94 22 Figure 2.2-6 8/93 20 2.1-14 4/94 22 Figure 2 .2-7 8/93 20 2.1-15 4/94 22 Figure 2.2-8 8/93 20 2.1-16 4/94 22 Figure 2.2-9 8/93 20 2.1-17 4/94 22 Figure 2.2-10 8/93 20 2.1-18 4/94 22 Figure 2.2-11 8/93 20 2.1-19 4/94 22 Figure 2.2-12 8/93 20 2.1-20 4/94 22 Figure 2 .2-13 8/93 20 2.1-21 4/94 22 Figure 2.2-14 8/93 20 2.1-22 4/94 22 Figure 2.2-15 8/93 20 2.1-23 4/94 22 Figure 2.2-16 8/93 20 2.1-24 4/94 22 Figure 2.2-17 8/93 20 2.1-25 4/94 22 Figure 2.2-18 8/93 20 2.1-26 4/94 22 Figure 2.2-19 8/93 20 Figure 2.1-1 4/94 22 Figure 2.2-20 8/93 20 Figure 2.1-2 4/94 22 Figure 2.2-21 6/83 1 Figure 2.1-3 4/94 22 2.3-1 6/83 1 Figure 2.1-4 4/94 22 2 .3-2 6/83 1 Figure 2.1-5 4/94 22 2 .3-3 6/83 1 Figure 2.1-6 4/94 22 2.3-4 6/83 1 Figure 2.1-7 4/94 22 2.3-5 12/94 23 Figure 2.1-8 4/94 22 2.3-6 12/94 23 Figure 2.1-9 4/94 22 2.3-7 12/94 23 Figure 2.1-10 4/94 22 2 .3-8 12/94 23 Figure 2 .1-11 4/94 22 2 .3-9 12/94 23 Figure 2.1-12 4/94 22 2.3-10 12/94 23 Figure 2.1-13 4/94 22 2 .3-11 12/94 23 Figure 2.1-14 4/94 22 2.3-12 12/94 23 Figure 2.1-15 4/94 22 2 .3-13 12/94 23 Figure 2.1-16 4/94 22 2.3-14 12/94 23 Figure 2.1-17 4/94 22 2.3-15 6/83 1 2.2-1 8/93 20 2.3-16 12/94 23 2.2-2 8/93 20 2.3-17 12/94 23 2.2-3 8/93 20 2.3-18 6/83 1 2.2-4 8/93 20 2.3-19 6/83 1 2.2-5 8/93 20 2.3-20 6/83 1 2.2-6 8/93 20 2.3-21 6/83 1 2.2-7 8/93 20 2.3-22 12/94 23 2.2-8 8/93 20 2.3-23 6/83 1 2.2-9 8/93 20 Figure 2 .3-1 7/82 Originai 2.2-10 8/93 20 Figure 2.3-2 7/82 Original 2.2-11 8/93 20 Figure 2.3-3 7/82 Original 8/93 20 Figure 2.3-4 7/82 Original 2.2-12 2 .2-13 8/93 20 Figure 2 .3-5 7/82 Original 2.2-14 8/93 20 Figure 2 .3-6 12/94 23

• 2.2-15 8/93 20 Figure 2 .3-7 12/94 23 2.2-16 8/93 20 Figure 2.3-8 7/82 Original 2.2-17 8/93 20 Figure 2.3-9 7/82 Original

• 20 2.2-18 8/93 J

• REVISION 24 10/95 SPS UFSAR LEP-3 LIi? Ql . BllBC?UZB PAGEi

• R.A..sa VOLUME I Figure 2.3-10 Figure 2.3-11 J2JLU (continued) 3/94 3/94 B*viaion 21 21

.2..AJl.e.

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7/82 6/83 6/83 6/83 Reyiaion Original 1

1 1

2.4-1 6/83 1 Figure 2.4-lc 6/83 1 2.4-2 6/83 1 Figure 2.4-2 7/82 Original 2.4-3 6/83 1 Figure 2.4-3 7 /82 Original 2.4-4 6/83 1 Figure 2.4-4 7/82 Original 2.4-5 6/83 1 Figure 2.4-5 7/82 Original 2.4-6 6/83 1 Figure 2.4-6 7/82 Original 2.4-6a 6/83 1 Figure 2.4-7 7/82 Original 2.4-6b 6/83 1 Figure 2.4-8 7/82 Original 2.4-6c 6/83 1 Figure 2.4-9 7/82 Original 2.4-6d 6/83 1 Figure 2.4-10 7/82 Original 2.4-6e 6/83 1 Figure 2.4-11 7/82 Original 2.4-6f 6/83 1 Figure 2.4-12 7/82 Original 2.4-7 7/82 Original Figure 2.4-13 7/82 Original 2.4-8 6/83 1 Figure 2.4-14 7/82 Original 2.4-9 7/82 Original Figure 2.4-15 7/82 Original 2.4-10 7/82 Original Figure 2.4-16 7/82 Original

2. 4-11 7/82 Original Figure 2.4-17 7/82 Original 2.4-12 7 /82 Original Figure 2.4-18 7/82 Original 2 .4-13 6/83 1 Figure 2.4-19 7/82 Original 2.4-14 7/82 Original 2.5-1 6/83 1 2.4-15 7/82 Original 2.5-2 6/83 1

• 2.4-16 7/82 Original 2.5-3 6/83 1 2.4-17 7/82 Original 2.5-4 6/83 1 2.4-18 7/82 Original 2.5-5 6/83 1 2.4-19 7/82 Original 2.5-6 6/83 1 2.4-20 7/82 Original 2.5-7 6/83 1 2.4-21 7/82 Original 2.5-8 6/83 1 2.4-22 7 /82 Original 2.5-9 6/83 1 2.4-23 7 /82 Original 2.5-10 6/83 1 2.4-24 7 /82 Original 2.5-11 6/83 1 2.4-25 7 /82 Original 2.5-12 6/83 1 2.4-26 3/94 21 2.5-13 2/93 19 2.4-27 7/82 Original 2.5-14 6/83 1 2.4-28 7/82 Original 2.5-15 6/83 1 2.4-29 7/82 Original 2.5-16 6/83 . 1 2.4-30 7/82 Original 2.5-17 .6/83 1 2.4-31 7/82 Original 2.5-18 6/83 1 2.4-32 7/82 Original 2.5-19 6/83 *l 2.4-33 6/83 1 2.5-20 6/83 1 2.4-34 6/83 1 2.5-21 6/83 1 2.4-35 6/83 1 2.5-22 6/83 1 2.4-36 6/83 1 2.5-23 6/83 1 2.4-36a 6/83 1 2.5-24 6/83. Blank 2.4-36b 6/83 1 2.5-25 6/83 1 2.4-37 7/82 Original 2.5-26 6/83 1 2.4-38 7/82 Original 2.5-27 6/83 1 2.4-39 7/82 Original 2.5-28 6/83 1 2.4-40 7/82 Original 2.5-29 6/83 1 6/83 1 2.4-41 2/93 .19 2.5-30 2.4-42 7/82 Original 2.5-31 6/83 1 2.4-43 7/82 Original 2.5-32 6/83 1 2.4-44 7/82 Original 2.5-33 6/83 1 2.4-45 7/82 Original 2.5-34 6/83 1 2.4-46 7/82 Original 2.5-35 6/83 1 Original Figure 2.5-1 6/83 1 "

2.4-47 7/82

SPS UFSAR LEP-4 REVISION 24 10/95 ,,

wxsi Ql llllCiUZI iA~BS bJa VOLUME I Figure Figure 2.5-la 2.5-2 Jail (continued) 6/83 7/82 Rayiaion 1

Original bJiJt Figure 3.3-6 Figure 3.3-7 Figure 3.3-8 Figure 3.3-9 J2Jlll 7/82 7/82 7/82 7/82 Raviaion Original Original Original Original Figure 2 .5-3 7/82 Original 3.4-1 4/91 13 Figure 2.5-4 7/82 Original 3.4-2 4/91 13 Figure 2.5-5 7/82 Original 3.4-2a 10/95 24 3.4-2b 4/91 13

~ll51.J2t!U: 3 3.4-2c 4/91 13 3.4-3 7/82 Original 3-i 4/91 13 3.4-4 10/95 24 3-ii 4/91 13 3.4-5 4/91 13 3-iii 4/91 13 3.4-5a 4/91 13 3-iv 4/91 13 3.4-6 4/91 13 3-v 4/91 13 3.4-7 4/91 13 3-vi 4/91 13 3.4-8 4/91 13 3-vii 4/91 13 3.4-9 4/91 13 3-viii 7/82 Original 3.4-10 4/91 13 3.1-1 10/95 24 3 .4-11 4/91 13 3.2-1 4/91 13 3. 4-lla 6/85 3 3.2-2 4/91 13 3.4-12 4/91 13 3.2-3 10/95 24 3.4-13 3/94 21 3.2-4 4/91 13 3.4-13a 3/94 21 3.2-5 7/82 original 3.4-14 3/94 21 3.2-6 4/91 13 3.4-15 7/82 Original 3.2-7 3/94 21 3.4-16 10/95 24 3,2-7a 3/94 21 3.4-16a 3/94 21

• 3 .2-7b 3/94 21 3.4-17 3/88 7.

3.2-8 12/94 23 3.4-18 7/82 Original 3.2-9 7/82 Original 3.4-19 10/95 24 3.2-10 3/94 21 3.4-20 7/82 Original 3.3-1 6/91 14 3.4-20a 3/94 21 3 .3-2 7/82 original 3.4-21 7/82 Original 3 .3-3 3/88 7 3.4-22 4/91 13 3.3-4 7/82 Original 3.4-23 6/83 1 3.3-5 12/94 23 Figure 3.4-1 7/82 Original 3.3-6 3/88 7 Figure 3.4-2 7/82 Original 3.3-6a 3/88 7 Figure 3 .4-3 7/82 Original 3.3-7 7/82 original Figure 3.4-3a 4/91 13 3.3-8 7/82 Original Figure 3.4-4 7/82 Original 3.3-9 7/82 Original Figure 3.4-5 7/82 Original 3.3-10 7/82 Original Figure 3.4-6 .. 7/82 Original 3.3-11 12/94 23 Figure 3 .4-7 4/91 13 3.3-12 8/90 10 Figure 3.4-8 4/91 13 3.3-13 6/91 14 Figure 3.4-9 4/91 13 3.3-14 10/95 24 Figure 3.4-10 7/82 Original 3.3-14a 12/94 23 Figure 3.4-11. 7/82 Original 3.3-15 12/94 23 Figure 3.4-12 7/82 Original 3.3-16 6/91 14 3.5-1 10/95 24 3.3-17 6/86 4 3.5-2 7/82 Originai 3.3-18 3/88 7 3.5-3 7/82 Original 3.3-19 6/83 1 3.5-4 7/82 Original 3.5-5 7/82 Original 3.3-20 7/82 Original 3.3-21 7/82 Original 3.5-6 7/82 Original Figure 3.3-1 7/82 Original 3.5-7 7/82 Original Figure 3.3-2 7/82 O'°iginal 3.5-8 7/82 Original Figure 3 .3-3 7/82 Original 3.5-9 7/82 Original Figure 3.3-4 6/91 14 3.5-10 10/95 24 Figure 3.3-5 7/82 Original 3.5-lOa 10/95 24

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REVISION 24 10/95 SPS UFSAR LEP-5 x,:rsT Ql lll1C2:+~I iA~IS

• ~

VOLUME I 3 .5-11 3.5-12 (continued)

.12.Au 10/95 7/82 geyiaion 24 Original R..11...sa 3.6-5 3.6-6 3.6-7 J2.A.il.

6/91 12/94 6/91 Rayiaion 14 23 14 3.5-13 10/95 .24 VOLUME II 3.5-14 10/95 24 3.5-14a 10/95 24 chapter 4 3.5-14b 10/95 .24 3.5-15 7/82 Original 4-i 7/82 Original 3.5-16 7/82 Original 4-ii 6/83 1 3.5-17 7/8.2 Original 4-iii 6/91 14 3.5-18 6/86 4 4-iv 6/83 1 3.5-18a 2/93 19 4-v 8/90 10 3.5-19 2/93 19 4-vi 8/90 10 3.5-20 2/93 19 4-vii 12/90 12 3.5-21 2/93 19 4.1-1 7/82 Original 3.5-2la 12/94 23 4.1-2 8/89 8 3.5-22 12/94 23 4.1-3 7/82 Original 3.5-23 7/82 Original 4.1-4 2/93 19 3.5-24 12/94 23 4.1-5 8/89 8 3.5-25 10/95 24 4.1-6 8/89 8 3.5-26 2/93 19 4.1-7 7/82 Original 3.5-27 12/94 23 4.1-8 7/82 Original 3.5-28 7/82 Original 4.1-9 8/90 10 3.5-29 7/82 Original 4.1-10 8/90 10 3.5-30 7/82 Original 4.1-11 2/93 19 3.5-31 7/82 Original 4.1-12 2/93 19 3.5-32 7/82 Original 4.1-13 7/82 Original 3.5-33 7/82 Original 4.1-14 7/82 Original 3.5-34 6/86 4 4.1-15 8/90 10 3.5-35 7/82 Original 4.1-16 8/90 10 3.5-36 7/82 Original 4.1-17 7/82 ,Original 3.5-37 10/95 24 4.1-18 6/92 17 3.5-37a 10/95 24 4.l-18a 2/93 19 3.5-38 6/86 Blank 4.1-18b 2/93 19 3.5-39 6/86 4 4.1-19 6/92 17 3.5-40 7/82 Original 4.1-20 2/93 19 3.5-41 7/82 Original 4.1-21 7/82 Original 3.5-42 7/82 Original 4.1-22 7/82 Original Figure 3.5-1 7/82 Original 4.1-23 7/82 Original Figure 3.5-2 7/82 Original 4.1-24 7/82 Original Figure 3.5-3 7/82 Original 4.1-25 7/82 Original Figure 3.5-4 7/82 Original 4.1-26 7/82 Original Figure 3.5-5 10/95 24 4.1-27 4/91 13 Figure 3.5-6 7/82 Original 4.1-28 7/82 Original Figure 3.5-7 7/82 Original 4.1-29 4/91 13 Figure 3.5-8 7/82 Original 4.1-30 7/82 Original Figure 3.5-9 7/82 Original 4.1-31 8/90 10 Figure 3.5-9a 12/94 23 4.1-32 2/93 19 Figure 3.5-10 7/82 Original 4.1-33 2/93 19 Figure 3 .5-11 7/82 Original 4.1-34 8/90 10 Figure 3.5-12 8/93 20 Figure 4.1-1 7/82 Original Figure 3.5-13 7/82 Original Figure 4.1-2 7/82 Original

• Figure 3.5-14 Figure 3.5-15 3.6-1 3.6-2 3 .6-3 3.6-4 12/94 12/94 6/91 7/82 6/91 6/91 23 23 14 Original 14 14 4.2-1 4.2-2 4.2-3 4.2-3a 4.2-4 4.2-5 6/84 7/82 6/87 6/87 7/82 6/84 2

Original 6

6 Original 2

REVISION 24 10/95 SPS UFSAR LEP-6 LJ:&U:~ QE IElli~iJ:JZB 2a,g1s

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4.2-5a 4.2-6 12.All VOLUME II (continued) 6/84 12/94 Revision 2

23

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4.3-5 4.3-6 4.3-7 4 .3-8 l2.A..U.

8/89 7/82 8/89 7/82 Reyiaion 8

Original 8

Original 4.2-6a 6/84 2 4 .3-9 7/82 Original 4.2-7 7/82 Original 4.3-10 7/82 Original 4.2-8 4/91 13 4.3-11 7/82 Original 4.2-9 7/82 Original 4 .3-12 7/82 Original 4.2-10 7/82 Original 4.3-13 7/82 Original 4.2-11 7/82 Original 4.3-14 7/82 Original 4.2-12 7/82 Original 4.3-15 7/82 Original 4.2-13 7/82 Original 4.3-16 6/91 14 4.2-14 6/83 1 4.3-16a 6/91 14 4.2-15 6/83 1 4.3-17 6/91 . 14 4.2-16 7/82 Original 4.3-18 10/95 24 4.2-17 3/94 21 4.3-19 6/83 1 4.2-18 3/94 21 4.3-20 6/83 1 4.2-19 3/94 21 4.3-21 8/90 10 4.2-19a 3/94 21 4.3-22 6/91 14 4.2-20 10/95 24 4.3-23 6/83 1 4.2-20a 4/91 13 4.3-24 6/83 1 4.2-21 8/89 8 4.3-25 8/90 10 4.2-22 6/83 1 4.3-26 8/90 10 4.2-23 8/90 10 Figure 4.3-1 7/82 Original 4.2-24 6/92 17 Figure 4 .3-2 7/82 Original 4.2-25 4/91 13 .Figure 4.3-3 7/82 Original 4.2-26 6/83 1 Figure 4 .3-4 7/82 Original 4.2-27 8/89 8 Figure 4.3-5 7/82 Original 4.2-28 6/83 1 4.4-1 7/82 Original 4.2-29 3/94 21 4 .4-2 7/82 Original 4.2-30 8/89 8 4.4-3 7/82 Original 4.2-31 6/83 1 4.4-4 7/82 Original 4.2-32 6/83 1 4.4-5 7/82 Original 4.2-33 3/94 21 4.4-6 7/82 Original 4.2-34 6/83 1 4.4-7 7/82 Original 4.2-35 6/83 .1 4.4-8 6/83 1 4.2-36 8/89 8 4.4-9 7/82 Original 4.2-37 6/83 1 4.4-10 7/82 Original 4.2-38 6/83 1 4 .4-11 7/82 Original 4.2-39 11/90 11 4.4-12 7/82 Original 4.2-40 6/83 1 4.2-41 6/83 1 Cbal;lt!ii:: 5 4.2-42 6/83 1 Figure 4.2-1 3/94 21 5-i 6/84 2 Figure 4.2-2 10/95 24 5-ii 2/93 19 Figure 4.2-3 7/82 original 5-iii 7/82 Original Figure 4.2-4 7/82 Original 5.1-1 2/93 19.

Figure 4.2-5 7/82 Original 5.1-2 2/93 19 Figure 4.2-6 7/82 Original 5.1-3 8/90 10 Figure 4.2-7 7/82 Original 5.2-1 7/82 Original Figure 4.2-8 7/82 Original 5.2-2 12/94 23 Figure 4.2-9 7/82 Original 5.2-3 12/94 23 Figure 4.2-10 7/82 Original 5.2-3a 12/94 23 Figure 4 .2-11 7/82 Original 5.2-4 12/94 23 Figure 4.2-12 7/82 O:figinal 5.2-5 12/94 23 4.3-1  ?/82 original 5.2-6 12/94 23 4.3-2 7/82 Original 5.2-7 12/94 23 4.3-3 7/82 Original 5.2-8 12/94 23 4.3-4 7/82 Original 5.2-9 12/94 23 J

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REVISION 24 10/95 SPS UFSAR LEP-7 LJ:ii Ql 1ll1CiI3ZI 2A~li

• .2..A..sa.

5.2-10 5.2-11 J2.Lt.Jt VOLUME II (continued) 6/92 6/92 Revision 17 17

~

5.2-67 Figure 5.3-1 5 .3-2 5.3-3 5.2-1 J2.Lt.Jt 12/94 6/92 10/92 7/82 6/92 Reyiaion 23 17 18 Original 17 5.2-12 12/94 23 5.2-13 12/94 23 5.3-4 10/92 18 5.2-14 12/94 23 5.3-5 ?194 21 5.2-15 12/94 23 5.3-6 6/92 17 5.2-16 12/94 23 5 .3-7 6/92 17 5.2-17 12/94 23 5.3-8 6/92 17 5.2-18 12/94 23 5.3-9 6/92 17 5.2-19 12/94 23 5.3-10 6/92 17 5.2-20 12/94 23 5.3-11 6/92 17 5.2-21 12/94 23 5.3-12 3/94 21 5.2-22 12/94 23 5.3-13 3/94 21 5.2-23 12/94 23 5.3-14 6/92 17 5.2-24 12/94 23 5.3-15 6/92 17 5.2-25 12/94 23 5.3-16 6/92 17 5.2-26 12/94 23 5.3-17 6/92 17 5.2-27 12/94 23 Figure 5.3-1 7/82 Original 5.2-28 12/94 23 Figure 5 .3-2 6/92 17 5.2-29 12/94 23 Figure 5.3-3 7/82 Original 5.2-30 12/94 23 5.4-1 2/93 19 5.2-31 12/94 23 5.4-2 2/93 19 5.2-32 12/94 23 5.4-3 2/93 19 5.2-33 12/94 23 5.4-4 2/93 19 5.2-34 12/94 23 5.4-5 2/93 19 5.2-35 12/94 23 5.4-6 2/93 19 5.2-36 12/94 23 5.4-7 2/93 19 5.2-37 12/94 23 5.4-8 2/93 19 5.2-38 12/94 23 5.4-9 2/93 19 5.2-39 12/94 23 5.4-10 2/93 19 5.2-40 12/94 23 5.4-11 2/93 19 5.2-41 12/94 23 5.4-12 2/93 19 5.2-42 12/94 23 5.4-13 2/93 19 5.2-43 12/94 23 5.4-14 2/93 19 5.2-44 12/94 23 5.5-1 6/92 17 5.2-45 12/94 23 5.5-2 12/94 23 5.2-46 12/94 23 5.5-3 12/94 23 5.2-47 12/94 23 5.5-4 12/94 23 5.2-48 12/94 23 5.5-5 12/94 23 5.2-49 12/94 23 5.5-6 12/94 23 5.2-50 12/94 23 5.5-7 12/94 23 5.2-51 12/94 23 5.5-8 6/92 17 5.2-52 12/94 23 5.2-53 12/94 23  !:bst?t~.: 6 5.2-54 12/94 23 6-i 6/85 3 5.2-55 12/94 23 6-ii 2/93 19 5.2-56 12/94 23 6-iii 6/83 1 5.2-57 12/94 23 6-iv 2/93 19 5.2-58 12/94 23 6-v 2/93 19 5.2-59 12/94 23 6.1-1 7/82 Original 5.2-60 12/94 23 6.1-2 11/90 11

• 5.2-61 12/94 23 6.1-3 7/82 Original 5.2-62 12/94 23 6.1-4 7/82 Original 5~2-63 12/94 23 6.1-5 7 /82 Original 5.2-64 12/94 23 Figure 6.1-1 6/85 3 5.2-65 12/94 23 6.2-1 10/95 24 C, 5.2-66 12/94 23 6.2-2 6/85 3

REVISION 24 10/95 SPS UFSAR LEP-8 LlS:t Ql BlllC:tUZI i:!.l~IS

~

6.2-3 6.2-4 J2.All VOLUME II (continued) 6/85 10/92 Raviaion 3

18

.2.AJa 6.2-56 6.2-57 6.2-58 6.2-59 J2.A.ll 10/95 6/85 7/82 7/82 Reyiaion 24 3

Original Original 6.2-5 2/93 19 6.2-60 12/94 23 6.2-6 3/94 21 6.2-61 6/85 3 6.2-7 12/94 23 6.2-62 3/94 21 6.2-8 2/93 19 6.2-63 10/92 18 6.2-9 3/94 21 6.2-64 7/82 Original 6.2-10 2/93 19 6.2-65 6/85 3 6.2-lOa 2/93 19 6.2-66 6/85 3 6.2-11 2/93 19 6.2-67 7/82 Original 6.2-12 3/94 21 6.2-68 6/85 3 6.2-12a 3/94 21 6.2-69 7/82 Original 6.2-13 10/95 24 6 .2-70 3/94 21 6.2-14 6/85 3 6 .2-71 3/94 21 6.2-15 2/93 19 6.2-72 3/94 21 6.2-16 2/93 19 6.2-73 2/93 19 6.2-17 2/93 19 6.2-74 2/93 19 6.2-18 2/93 19 Figure 6.2-1 3/94 21 6.2-19 2/93 19 Figure 6.2-2 3/94 21 6.2-20 2/93 19 Figure 6.2-3 3/94 21 6.2-21 3/94 21 Figure 6.2-4 3/94 21 6.2-22 2/93 19 Figure 6.2-5 7/82 Original 6.2-23 8/89 8 Figure 6.2-6 8/93 20 6.2-24 10/92 18 Figure 6.2-7 8/93 20 6.2-25 2/93 19 Figure 6.2-8 8/93 20 6.2-26 2/93 19 Figure 6.2-9 8/93 20 6.2-27 2/93 19 Figure 6.2-10 8/93 20 6.2-28 2/93 19 Figure 6.2-11 8/93 20 6.2-29 6/83 1 6 .3-1 10/95 24 6.2-30 2/93 19 6.3-2 3/92 16 6.2-31 2/93 19 6.3-3 2/93 19 6.2-32 8/93 20 6 .3-4 2/93 19 6.2-33 2/93 19 6.3-4a 8/90 10 6'. 2-34 8/93 20 6.3-5 3/94 21 6.2-35 7/82 Original 6.3-5a 3/94 21 6 .2-36 2/93 19 6.3-6 2/93 19 6.2-37 2/93 19 6.3-6a 2/93 19 6.2-38 2/93 19 6 .3-7 12/94 23 6.2-39 10/92 18 6. 3-7a 12/94 23 6.2-40 3/94 21 6 .3-7b 12/94 23 6.2-41 3/94 21 6 .3-8 2/93 19

' 6.2-42 2/93 19 6 .3-9 8/93 20 6.2-43 2/93 19 6.3-9a 2/93 19 6.2-44 2/93 19. 6.3-10 6/83 1 6.2-44a 2/93 19 6.3-11 3/94 21 6.2-45 2/93 19 6 .3-12 11/90 11 6.2-46 2/93 19 6 .3-13 2/93 19 6.2-47 10/95 24 6.3-14 10/95 24 6.2-47a 10/95 24 6.3-14a 10/95 24 6.2-48 7/82 Original 6.3-15 10/95 24 6.2-49 10/95 24 6.3-16 2/93 19

~

6.2-50 6.2-51 6.2-52 6.2-53 6.2-54 6.2-55 10/95 11/90 3/94 6/85 3/94 3/94 24 11

• 21 3

21 21 6.3-16a 6.3-17 6.3-18 6.3-18a 6 .3-19 6.3-20 11/90 6/83 2/93 12/94 3/92 7/82 11 1

19 23 16 Original

-=--=----;=..------~;=..:=..~~===-~~

REVISION 24 10/95 SPS UFSAR LEP-9

• L:Z:12: Ql BEEBCf:Z:lZI 21.!;;BI

• . .2.A.sa VOLUME II (continued) 6.3-21 6.3-22

.12.A.U.

2/93 7/82 Rayiaion 19 Original

.2.A.sa 7.2-30 7.2-30a 7.2-31 7.2-32 7.2-33 Iau.

2/93 2/93 2/93 12/94 3/94 Raviaion 19 19 19 23 21 6.3-23 6/83 1 6.3-24 3/94 21 7.2-34 3/94 21 6.3-25 7/82 Original 7.2-34a 4/91 13 6.3-26 7/82 Original 7.2-35 2/93 19 6.3-27 2/93 19 7 .2-36 10/95 24 Figure 6.3-1 3/92 16 7.2-36a 10/95 24 Figure 6.3-2 6/83 1 7.2-37 7/82 Original Figure 6.3-3 7/82 Original 7.2-38 2/93 19 Figure 6.3-4 3/92 16 7.2-38a 2/93 19 Figure 6.3-5 7/82 Original 7.2-39 2/93 19 Figure 6.3-6 7/82 Original 7.2-39a 2/93 19 7.2-39b 10/95 24 7.2-40 2/93 19

~baJ;!t!it:C: '1 7.2-41 7/82 Original 7/82 Original 7.2-42 7 /82 Original 7-'i 2/93 19 7.2-43 2/93 19 7-ii 2/93 19 7.2-44 7/82 Original 7-iia 7/82 Original 7.2-45 7/82 Original 7-iii 2/93 19 7.2-46 7/82 Original 7-iv 6/83 1 7.2-47 6/91 14 7-v 6/83 1 7.2-48 6/91 14 7-vi 2/93 19 7.2-48a 6/91 14 7-vii 8/90 10 7.2-49 7/82 Original 7-viii 8/90 10 7.2-50 7/82 original 7-ix 7:1-1 7/82 Original Figure 7.2-1 4/91 13 2/93 19 Figure 7.2-2 2/93 19 7.2-1 2/93 19 Figure 7.2-3 7/82 Original 7.2-2

• I 6/91 14 Figure 7.2-4 7/82 Original 7.2-3 I 4/91 13 Figure 7.2-5 7/82 Original 7.2-4 7.2-5 7/82 Original Figure 7.2-6 6/85 3 2/93 19 Figure 7.2-7 7/82 Original 7.2-6 7/82 Original Figure 7.2-8 7/82 Original 7.2-7 7/82 Original Figure 7.2-9 7/82 Original 7.2-8 7.2-9 2/93 19 Figure 7.2-10 3/94 21 7;2-10 2/93 19 Figure 7.2-11 7/82 Original

7. 2-11 7/82 Original Figure 7.2-12 7/82 Original 7 ;2-12 4/91 13 Figure 7.2-13 2/93 19

7. 2-13 2/93 19 7.3-1 3/94 21 7.2-14 6/91 14 7.3-2 2/93 19 2/93 19 7 .3-3 2/93 19 7.2-15 7.2-16 6/91 14 7.3-4 3/94 21 7.2-17 7/82 Original 7.3-5 2/93 13 7/82 Original 7.3-6 7/82 Original 7.2-18 7.2-19 7/82 Original 7 .3-7 2/93 19 2/93 19 7.3-8 4/91 13 7.2-20 2/93 19 7 .3-9 7/82 Original 7.2-21 7.2-2la 6/85 3 7.3-10 7/82 Original 7.2-22 8/93 20 7.3-11 2/93 19 3/92 16 7. 3-12 2/93 19 7.2-23 7.2-24 3/94 21 7 .. 3-13 2/93 19 3/94 Blank 7.3-14 2/93 19 7.2-25 3/94

• 21 7.3-15 2/93 19 ~ I 7.2-26 3/92 16 7.3-16 2/93 19 7.2-27 7/82 Original Figure 7.3-1 3/94 21 ,.

7.2-28 2/93 19 Figure 7.3-2 12/94 . 23 7.2-29

REVISION 24 10/95 SPS UFSAR LEP-10

,. , .1 L:CSf Ql BllliCi:CJZI 2A~1iS b.su.

Figure 7 .3-3 7.4-1 7.4-2 12.AU VOLUME II (continued) 7/82 8/90 2/93 Revision Original 10 19 bn.

7.5-21a 7.5-22 7 5-22a 7.5-23 7.5-24 Jail.

6/84 8/93 6/83 7/82 2/93 Ravipion 2

20 1

Original 19 7.4-3 7/82 Original 7.5-25 3/92 16 7.4-4 2/93 19 7.5-26 6/85 3 7.4-5 6/91 14 7.5-27 6/85 3 7.4-6 7/82 Original 7.5-28 7 /82 Original 7.4-7 8/93 20 7.5-29 6/83 1 7.4-8 7/82 original 7.5-30 6/83 1 7.4-9 2/93 19 7.5-31 10/92 18 7.4-10 2/93 19 7.5-32 3/94 21 7.4-11 7/82 Original 7.5-33 7/82 Original 7.4-12 7/82 Original 7 .4-34 7/82 Original

7. 4-13 2/93 19 7 _5..:35 6/91 14 7.4-14 7/82 Original 7.5-36 7/82 Original 7.4-15 10/95 24 Figure 7.5-1 7/82 Original 7.4-16 7/82 Original Figure 7.5-2 7/82 Original 7.4-17 2/93 19 Figure 7.5-3 7/82 Original 7.4-18 2/93 19 Figure 7.5-4 7 /82 Original 7.4-19 7/82 Original 7.6-1 2/93 19 7.4-20 7/82 Original 7.6-2 2/93 19 7.4-21 2/93 19 7.6-3* 8/90 10 7.4-22 2/93 19 7.6-4 2/93 19 7 .4-'23 2/93 19 Figure 7.6-1 8/90 10 7.4-24 2/93 19 Figure 7.6-2 7/82 Original 7.4-25 2/93 19 7.7-1 8/93 20 7.4-26 7/82 Original 7.7-2 12/94 23 7.4-27 7/82 Original 7.7-3 6/83 1 7.4-28 7/82 Original 7.7-4 8/93 20 7.4-29 6/91

• 14 7.7-5 8/93 20 7.4-30 7/82 Original 7.7-6 8/93 20 Figure 7.4-1 8/93 20 7.7-7 6/91 14 Figure 7.4-2 7/82 Original 7.7-8 6/91 14 Figure 7.4-3 8/90 10 7.7-8a 6/91 14 7.5-1 8/93 20 7 7-9 3/88 7 7.5-2 8/93 20 7.7-9a 3/88 7 7.5-2a 8/93 20 7 7-10 8/93 20 7.5-3 12/91 15 Figure 7.7-1 12/94 23 7.5-4 12/91 15. 7.8-1 8/89 8 7.5-5 12/91 15 7.8-2 7/82 Original 7.5-6 6/91 14 7.8-3 7/82 Original 7.5-7 8/93 20 7.8-4 7/82 Original 7.5-8 7/82 Original Figure 7.8-1 7/82 Original 7.5-9 8/93 20 Figure 7.8-2 7/82 Original 7.5-10 8/93 20 7.9-1 11/90 11 7.5-11 7/82 Original 7.9-2 11/90 11 7.5-12 8/93 20 7.9-3 7/82 Original

7. 5-13 6/90 9 7.10-1 8/90 10 7.5-13a 6/91 14 7.10-2 8/90 10 7.5-14 6/83 1 7.10-3 8/90 10 7.5-15 6/83 1 7.10-4 8/90 10 7.5-16 6/83 1. 7.10-4a 8/90 10 7.5-17 6/83 1 7.10-5 8/90 10 7.5-18 8/93 20 7.10-6 8/90 10 7.5-19 6/83 1 7.10-7 8/90 10 7.5-20 6/83 1 7.10-8 8/90 10 7.5-21 3/88 7 Figure 7.10-1 8/90 10

!==-~=~==~~~- = ~-=-~~~-~~~--

REVISION 24 10/95 SPS UFSAR LEP-11 LX&i Ql 1i:r:1cixu 2A~I&

• .I.Asa 7 .11-1 7 .11-2 12.AJi.Jl VOLUME II (continued) 8/90 8/90 Rayipion 10 10 b.sa

!:bgi;2te.: 2 9-i 12.AJi.Jl 7/82 Ravipion Original 7 .11-3 8/90 10 9-ii 7/82 Original 7.12-1 2/93 19 9-iii 7/82 Original 7.12-2 2/93 19 9-iv 6/91 14 9-v 6/83 1 VOLUME III 9-vi 12/94 23 9-vii 6/92 17 Cbapte;i;: s 9-viia 6/92 17 9-viii 6/92 17 8-i 6/83 1 9-ix 4/91 13 8-ii 6/83 1 9-x 6/83 1 8-iii 6/83 1 9-xi 8/90 10 8.1-1 8/93 20 9-xii 7/82 Original 8.1-2 7/82 Original 9-xiii 4/91 13 Figure 8.1-1 7/82 Original 9-xiv 12/90 12 8.2-1 10/92 18 9-xv 4/91 13 8.2-2 10/92 18 9.1-1 7/82 Original 8.2-3 8/93 20 9.1-2 7/82 Original 8.2-4 7/82 Original 9.1-3 6/85 3 8.3-1 10/95 24 9.1-4 10/92 18 8 .3-2 3/94 21 9.1-5 12/94 23 8 .3-3. 10/92 18 9.1-6 3/94 21

• 8.3-4 6/92 17 9.1-7 7/82 Original Figure 8.3-1 3/94 21 9.1-8 3/94 21 Figure 8.3-2 7/82 original 9.1-8a 2/93 19 8.4-1 10/92 18 9.1-9 12/86 5 .

8.4-2 3/94 21 9.1-9a 12/86 5 8.4-2a 8/93 20 9.1-10 10/92 18 8.4-3 10/95 24 9 .1-11 10/92 18 8.4-4 10/95 24 9.1-12 10/95 24 8.4-5 10/95 24 9.1-13 10/92 18 8.4-6 8/93 20 9.1-14 7/82 Original 8.4-7 12/94 23 9.1-15 7/82 Original 8.4-7a 3/92 16 9.1-16 7/82 Original Figure 8.4-1 3/94 21 9 .1-17 10/92

• 18 Figure 8.4-2 3/94 21 9.1-18 7/82 Original 8.5-1 3/94 21 9.1-19 7/82 Original 8.5-2 12/94 23 9.1-20 7/82 Original

8. 5-3 7/82 Original 9.1-21 7/82 Original 8.5-4 8/93 20 9.1-22 3/94 21 8.5-5 10/92 18 9.1-23 7/82 Original 8.5-6 10/92 18 9.1-24 7/82 Original 8.5-7 6/90 9 9.1-25 11/90 11 8.5-7a 10/92 . 18 9.1-26 4/91 13 8.5-8 10/92 18 9.1-27 6/85 3 8.5-9 3/94 21 9.1-28 8/93 20 8.5-10 3/94 21. 9.1-29 7/82 Original

8. 5-11 8/93 20 9.1-30 6/92 17 8.5-12 8/93 20 9.1-31 6/83 1 7/82 Original 8.5-13 6/83 1 9.1-32 8.5-14 10/92 18 9.1-33 12/94 23 8.5-15 6/83 1 9.1-33a 12/94 23 8.6-1 7/82 Original 9.1-34 7/82 Original 8.6-2 7/82 Original 9.1-35 10/95 24 8.6-3 7/82 Original 9.1-36 7/82 Original* ,

9.1-37 10/95 24'

REVISION 24 10/95 SPS UFSAR LEP-12 L:Ci2: Ql BllBC2::CXB 2AgJ!ia

~

9.1-38 9.1-39 J2Jl.t....9.

VOLUME III (continued) 7/82 12/94 Rayipion Blank 23

~

9.3-8 9 .3-9 9.3-10 9.3-11 12..U..2 7/82 7/82 7/82 7/82 Rayiaion Original original Original Original 9.1-40 6/92 17 9.3-12 3/94 21 9.1-41 3/94 21 9.3-13 7/82 Original 9.1-42 6/92 17 9.3-14 7/82 Original 9.1-43 12/94 23 Figure 9.3-1 3/94 21 9 .*1-44 11/90 11 9.4-1 7/82 Original 9.1-45 7/82 Original 9.4-2 12/94 23 9.1-46 7/82 Original 9.4-2a 12/94 23 9.1-47 7/82 Original 9.4-3 8/93 20 9.1-48 7/82 Original 9.4-4 7/82 Original 9.1-49 7/82 Original 9.4-5 8/93 20 9.1-50 7/82 Original 9.4-6 8/93 20 9.1-51 3/94 21 9.4-7 6/92 17 9.1-52 8/93 20 9.4-8 8/93 20 Figure 9.1-1 3/94 21 9.4-8a 6/86 4 Figure 9.1-2 3/94 21 9.4-9 7/82 Original Figure 9 .1-3 3/94 21 9.4-10 7/82 Original Figure 9.1-4 3/94 21 9.4-11 8/93 20 Figure 9.1-5 3/94 21 9.4-12 8/93 20 Figure 9.1-6 3/94 21 9.4-13 10/95 24 9.2-1 7/82 Original 9.4-13a 6/92 17 9.2-2 6/85 3 9.4-14 3/94 21 9.2-3 6/92 17 9.4-14a 12/91 15 9.2-4 6/92 17 9.4-15 7/82 Original 9.2-4a 6/92 17 9.4-16 3/92 16 9.2-5 6/83 1 9.4-17 8/90 . 10 9.2-6 6/92 17 9 ..4-18 7/82 Original 9.2-7 6/92 17 9.4-19 8/93 20 9.2-8 7/82 Original 9.4-20 8/93 20 9.2-9 6/92 17 9.4-20a 10/92 18 9.2-10 6/92 17 9.4-21 10/92 18 9.2-11 7/82 Original 9.4-22 10/92 18

.9.2-12 7/82 Original 9.4-23 7/82 Original 9.2-13 7/82 Original 9.4-24 7/82 Original 9.2-14 7/82 Original 9.4-25 7/82 Original 9.2-15 7/82 Original 9.4-26 7/82 Original 9.2-16 7/82 Original 9.4-27 7/82 Original 9.2-17 7/82 Original 9.4-28 7/82 Original 9.2-18 7/82 Original 9.4-29 8/93 20 9.2-19 6/92 17 9.4-30 7/82 Original 9.2-20 6/92 17 .9.4-31 7/82 Original 9.2-20a 6/92 17 9.4-32 11/90 11 9.2-21 7/82 Original 9.4-33 8/93 20 Figure 9.2-1 3/94 21 9.4-34 7/82 Original Figure 9 .2-2 3/94 21 9.4-35 7/82 Original Figure 9 .2-3 3/94 21 9.4-36 7/82 Origina~

Figure 9.2-4 3/94 21 Figure 9.4-1 3/94 21 9.3-1 7/82 *Original Figure 9.4-2 3/94 21 9.3-2 7/82 Original Figure 9.4-3 3/94 21 3/94 9 .3-3 8/93 20 Figure 9.4-4 21 9.3-3a 8/90 10 Figure 9.4-5 3/94 21 9.3-4 8/93 20 Figure 9.4-6 3/94 21 9.3-4a 6/86 4 Figure 9.4-7 3/94 21 9.3-5 8/93 20 Figure 9 .4-8

• 3/94 21 9 .3-6 8/93 20 Figure 9.4-9 3/94 21 9 .3-7 12/94 23 9.5-1 8/93 20 J

REVISION 24 10/95 SPS UFSAR LEP-13 L:tlf Q! B!!l,t:Z:li!I fAg1a

• ~

9.5-2 9.5-3

~

VOLUME III (continued) 8/93 7/82 Revision 20 Original

.i.AJa 9.8-2 9.8-3 9.8-4 9.8-5 J2.A.ll 6/85 6/83 6/83 12/94 7/82 Ravi.pion 3

1 1

23 Blank 9.5-4 7/82 Original 9.8-6 9.5-5 8/93 20 9.8-7 6/86 4 9.5-6 7/82 Original 9.8-8 7/82 Original 9.5-7 7/82 Original 9.8-9 7/82 Original 9.5-8 3/92 16 9.8-10 7/82 Original 9.5-9 6/92 17 Figure 9.8-1 3/94 21 9.5-10 6/92 17 Figure 9.8-2 3/94 21

9. 5-11 7/82 Original 9.9-1 8/90 10 9.5-12 7/82 Original 9.9-2 8/90 10 Figure 9.5-1 3/94 21 9.9-3 12/94 23 9.6-1 8/93 20 9.9-3a 12/94 23 9.6-2 8/93 20 9.9-3b 12/94 23 9.6-3 8/93 20 9.9-3c 10/95 24 9.6-4 3/92 16 9.9-3d 10/95 24 9.6-4a 8/93 20 9.9-4 8/90 10 9.6-5 6/84 2 9.9-4a 8/90 10 9.6-6 8/93 20 9.9-5 6/83 1 9.6-7 6/84 2 9.9-6 12/94 23 9.6-8 6/84 2 9.9-7 2/93 19 9.6-9 8/93 20 9.9-8 8/93 20 9.6-10 8/93 20 9.9-8a 12/94 23

9. 6-11 3/92 16 9.9-9 6/90 9 9.6-12 6/83 1 9.9-10 12/94 23 9.6-13 6/84 2 Figure 9.9-1 3/94 21 9.6-14 6/83 1 9.10-1 3/94

• 21

.9. 6-15 3/92 16 9.10-2 3/94 21 9.6-16 3/92 16 9.10-3 6/92 17 9.6-17 6/84 2 9.10-4 6/92 17 9.6-18 6/84 2 9.10-5 6/92 17 9.6-19 7/82 Original 9.10-6 6/92 17 9.6-20 8/93 20 9.10-7 6/92 17 9.6-21 6/84 2 9.10-8 2/93 19 Figure 9.6-1 3/94 21 9.10-9 6/92 17 Figure 9.6-2 3/94 21 9.10-10 6/92 17 Figure 9.6-3 3/94 21 9.10-11 6/92 17 Figure 9.6-3a 3/94 21 9.10-12 6/92 17 Figure 9.6-4 3/94 21 9.10-13 6/92 17 Figure 9.6-4a 3/94 21 9.10-14 *6/92 17 9.7-1 8/93 20 9.10-15 6/92 17 9.7-2 7/82 Original 9.10-16 6/92 17 9.7-3 8/93 20 9.10-17 6/92 17 9.7-4 8/93 20 9.10-18 6/92 17 9.7-5 6/83 1 9.10-19 6/92 17 9.7-6 7/82 Blank 9.10-20 6/92 17

9. 7-7 6/83 1 9.10-21 12/94 23 9.7-8 6/83 1 9.10-22 12/94 23 9.7-9 6/83 1- 9.10-23 10/95 24 9.7-10 3/92 16 9.10-24 6/92 17 6/83 1 9.10-25 6/92 17

9. 7-11 9.7-12 6/83 1 9.10-26 6/92 17 Figure 9.7-1 3/94 21 9.10-27 6/92 17 Figure 9.7-2 3/94 21 9.10-28 6/92 17 Figure 9.7-3 3/94 21 9.10-29 6/92 17 Figure 9.7-4 3/94 21 9.10-30 6/92 17 ~

9.8-1 6/83 1 9.10-31 6/92 17

REVISION 24 10/95 SPS UFSAR LEP-14 LIST OP EPPECTIYE PAGES

.P..A.sa 9.10-32 9.10-33 l2.A..ti VOLUME III (continued) 6/92 6/92 Rayiaion 17 17

.P..A.sa 9.12-7 9.12-8 9.12-9 9.12-10 la.u 8/93 8/93 8/93 8/93 Raviaion 20 20 20 20 9.10-34 6/92 17 9 .12-11 6/83 1 9.10-35 6/92 17

• 9 .12-12 10/95 24 9.10-36 6/92 17 9.12-13 10/95 24 9.10-37 6/92 17 9.12-14 10/95 24 9.10-38 6/92 17 9.12-15 10/95 24 9.10-39 12/94 23 9.12-16 10/95 24 9.10-40 6/92 17 9.12-17 2/93 19 9.10-41 6/92 17 9.12-18 6/83 1 9.10-42 6/92 17 9.12-19 8/93 20 9.10-43 6/92 17 9.12-20 8/93 20 9.10-44 6/92 17 9.12-21 8/93 20 9.10-45 6/92 17 9.12-22 8/93 20 9.10-46 6/92 17 9.12-23 8/90 10 9.10-47 6/92 17 Figure 9.12-1 7/82 Original 9.10-48 6/92 17 9 .13-1 8/93 20 9.10-49 6/92 17 9 .13-2 8/93 20 9.10-50 6/92 17 9.13-2a 8/93 20 9.10-51 6/92 17 9.13-3 8/93 20 9.10-52 6/92 17 9.13-4 10/95 24 9.10-53 6/92 17 9.13-5 8/93 20 9.10-54 6/92 17 9 .13-6 6/90 9 9.10-55 6/92 17 9.13-7 8/93 20 9.10-56 6/92 17 9 .13-8 4/91 13 9.10-57 6/92 17 9 .13-9 8/93 20 9.10-58 6/92 17 9.13-10 8/93 20 9.10-59 6/92 17 9.13-11 8/93 20 9.10-60 6/92 17 9.13-12 10/95 24 9.10-61 6/92 17 9 .13-12a 10/95 24 9.10-62 6/92 17 9.13-13 8/93 20 9.10-63 6/92 17 9.13-14 8/93 20 9.10-64 10/92 18 9.13-15 8/93 20 9.10-65 2/93 19 9 .13-16 6/90 9 9.10-66 6/92 17 9.13-16a 8/93 20 9.10-67 6/92 17 9.13-17 3/92 16 9.10-68 6/92 17 Figure 9.13-1 3/94 21 Figure 9.10-1 12/94 23 Figure 9.13-2 3/94 21 9 .11-1 4/91 13 Figure 9.13-3 3/94 21 9 .11-2 4/91 13 Figure 9 . 13 -4 3/94 21 9.11-2a (deleted) 4/91 13 9.14-1 12/94 23 9 .11-3 7/82 Original 9.14-2 12/94 23 Figure 9.11-1 3/94 21 9 14-3 8/90 10 Figure 9 .11-2 3/94 21 9.14-4 12/94 23 Figure 9.11-2a 3/94 21 9.14-5 12/94 23 Figure 9. ll-2b 3/94 21 Figure 9.14-1 3/94 21 Figure 9.ll-2c 3/94 21 9A-i 7/82 Original Figure 9.ll-2d 3/94 21 9A-ii 7/82 Blank Figure 9.11-2e 3/94 21 9A-iii 8/90 10 Figure 9.ll-2f 3/94 21 9A-iv 8/90 10 7/82 Original 9.12-1 8/93 20 9A-v 9.12-2 8/93 20 9A-1 8/90 10 9 .12-3 7/82 original 9A-2 8/90 Blank 9.12-4 8/93 20 9A-3 8/90 10 9.12-4a 8/93 20 9A-4 8/90 10 9.12-5 8/93 20 9A-5 8/90 10 9.12-6 7/82 original 9A-6 7/82 Blank

-..::=--::=o-=-=-="" - ~ - - - - - - - - - - - - -=a..=--==---=

REVISION 24 10/95 SPS UFSAR LEP-15 LI&% Ql Bl:E:BC%IlZ1 211.~as CJ

~ 12.LU B*vipion .2.A.Ja 12..A..la. B*vipion VOLUME III {continued) 10.1-1 7/82 Original 10.1-2 7/82 Blank 9A-7 7/82 Original 10.2-1 11/90 11 9A-8 7/82 Original Figure 10.2-1 3/94 21 9A-9 7/82 Original Figure 10.2-2 3/94 21 9A-10 7/82 Original Figure 10.2-3 3/94 21 9A-ll 7/82 Original Figure 10.2-4 3/94 21 9A-12 7/82 Original Figure 10.2-5 3/94 21 9A-13 7/82 Original Figure 10.2-6 3/94 21 9A-14 7/82 Original Figure 10.2-7 3/94 21 9A-15 8/90 10 Figure 10.2-8 3/94 21 9A-16 8/90 10 Figure 10.2-9 3/94 21 9A-17 8/90 10 Figure 10.2-10 3/94 21 "9A-18 8/90 10 10.3-1* 8/93 20 9A-19 8/90 10 10.3-2 8/93 20 9A-20 8/90 10 10.3-3 6/86 4 9A-21 8/90 10 10.3.,.4 8/93 20 9A-22 8/90 10 10.3-5 8/93 20 9A-23 7/82 Original 10.3-6 8/93 20 9A-24 7/82 Original 10.3-6a 8/93 20 9A-25 8/90 10 10.3-7 11/90 11 9A-26 8/90 10 10.3-8 8/93 20 Figure 9A-l 7/82 Original 10 .3-9 8/93 20 Figure 9A-2. 7/82 Original 10.3-10 8/93 20 9B-i 7/82 Original 10.3-lOa 8/93 20 9B-ii 7/82 Blank 10 .3-11 10/95 24 9B-iii 6/83 1 10.3-12 3/94 21 9B-l 6/87 6 10.3-12a 8/89 8 9B-2 7/82 Original 10 .3-13 8/93 20 9B-3 7/82 Original 10.3-14 3/94 21 9B-4 6/83 1 10.3-15 3/94 21 9B-5 6/83 1 10.3-16 7/82 Original 9B-6 6/83 1 10.3-17 3/94 21 9B-7 6/83 1 10.3-18 8/93 20 9B-8 6/83 Blank 10.3-19 8/93 20 9B-9 6/83 1 10.3-20 12/94 23 9B-10 6/83 1 10.3-21 3/94 21 9B-ll 6/83 1 10.3-22 3/94 21 9B-12 6/83 1 10.3-23 3/94 21 9B-13 6/83 1 10.3-24 12/94 23 9B-14 6/83 1 10.3-25 12/94 23 9C-i 12/94 23 10 .3-26 8/90 10 9C-l 12/94 23 10.3-27 8/93 20 9C-2 12/94 . 23 10 .3-28 12/94 23 9C-3 12/94 23 10.3-29 12/94 23 9C-4 12/94 23 10.3-29a 12/94 23 9C-5 12/94 23 10.3-30 8/93 20 9C-6 12/94 23 10.3-30a 8/93 20 9C-7 12/94 23 10 .3-31 7/82 Original 10.3-32 2/93 19 VOLUME IV 10.3-32a 8/93 20 10.3-33 6/83 1 10.3-34 4/91 13 chapter 10 10 .3-34a 6/83 1 10-i 8/93 20 10.3-35 6/83 1 10-ii 6/83 1. 10.3-36 3/94 21 10-iii 7/82 Original 10.3-37 2/93 19 10-iv 3/94 21 10 .3-37a 2/93 19 10-v 3/94 21 10.3-38 2/93 19

1-REVISION 24 10/95 SPS UFSAR LEP-16 L:IST QP ZPPECT:IVE PAGES (ji

~

10.3-39 10.3-40 J2.Ala VOLUME IV (continued) 6/90 2/93 Reyiaion 9

19

~

11.2-7 ll .2-7a ll.2-7b

.ll.2-7c

.12.A..U.

8/93 3/94 12/91 12/91 Reyiaion 20 21 15 15 10.3-40a 2/93 19 11.2-8 6/83 1 10.3-41 8/93 20 11 ~2-8a 8/93 20 10.3-42 6/83 1 11.2-9 8/93 20 10.3-43 8/93 20 11.2-10 7/82 Original 10.3-43a 8/89 8 11.2-11 7/82 Original 10.3-44 6/83 1 11.2-12 7/82 Original 10.3-45 12/94 23 11.2-13 7/82 Original 10.3-46 8/93 20 11.2-14 12/94 23 10.3-47 6/83 1 11.2-15 12/94 23 10.3-48 12/94 23 11.2-16 12/91 15 10.3-49 8/93 20 11.2-17 12/94 23 10.3-50 8/90 10 11.2-l 7a 12/94 23 10.3-51 8/93 20 11.2-18 8/93 20 10.3-52 6/83 1 11.2-18a 10/92 18 10.3:-53 8/93 20 11.2-18b 8/93 20 10.3-54 12/94 23 11.2-18c 12/91 15 10.3-55 7/82 Original 11.2-19 12/94 23 10.3-56 3/92 16 11.2-20 10/95 24 Figure 10.3-1 12/94 23 11.2-21 8/93 20 Figure 10.3-2 10/95 24 11.2-22 7/82 Original Figure 10.3-3 7/82 Original 11.2-23 7/82 Original Figure 10.3-4 7/82 Original 11.2.:.24 10/95 24 Figure 10.3-5 7/82 Original 11.2-25 12/94 23 Figure 10 .3-6 7/82 Original 11.2-26 12/94

• 23 Figure 10 .3-7 3/94 21 11.2-27 12/94 23 Figure 10 .3-8 3/94 21 11.2-28 . 7 /82 Original Figures 10.3-9 through 10.3-19 11.2-29 12/94 23 Deleted in Revision 21 dated 3/94 11.2-30 6/83 1 Figure 10.3-20 3/94 21 11.2-31 6/83 1 Figure 10.3-21 3/94 21 11.2-32 8/93 20 Figure 10.3-22 3/94 21 11.2-33 8/93 20 Figure 10 .3-23 3/94 21 11.2-34 7/82 Blank Figure 10.3-24 3/94 21 11.2-35 10/92 18 Figure 10.3-25 3/94 21 ll.2-35a 10/92 18 11.2-36 12/91 15 chapter ll 11.2-37 10/92 18 11.2-38 7/82 Original*

11-i 8/93 20 11.2-39 8/93 20 11-ii 12/91 15 11.2-40 12/91 15 11-iii 12/91 15 11.2-41 12/91 15 11-iiia 12/91 15 11.2-42 10/92 18 11-iv 4/91 13 11.2-42a 10/92 18 11-v 7/82 Original 11.2-43 12/91 15 11-vi 7/82 Original 11.2-44 7/82 Original 11-vii 12/91 15 11.2-45 7 /82

• Origina~

11.1-1 12/91 15 11.2-46 10/92 18 11.1-2 7/82 Original 11.2-47 10/92 18 11.2-1 12/94 23 11.2-48 12/91 15 1.1.2-2 12/91 15 11.2-48a 12/91 15 11.2-2a 8/93 20 11.2-48b 12/91 15 11.2-3 12/94 23 11.2-48c 12/91 15 11.2-4 12/94 23 ll.2-48d *12/91 15 11.2-5 3/92 16 11.2-48e 12/91 15 11.2-6 12/94 23 11.2-48f 12/91 15 ll.2-6a 12/94 23 ll.2-48g 12/91 15

_J

---

=-=--==---=-==-= - - - - - -

REVISION 24 10/95 SPS UFSAR LEP-17 LI&:C Ql Blll~?IJZB 2,M.ili

• -2.AJa 11.2-48h 11.2-48i J2.A.U.

VOLUME IV (continued) 12/91 12/91 Rayiaion 15 15 b.sa li.3-26 11.3-27 11.3-28 11.3-29 J2..A..t...9.

3/94 4/91 4/91 2/93 3/94 Rayiaion 21 13 13 19 21 11.2-48j 8/93 20 11.3-30 11.2-48k 12/91 15 11.3-31 3/94 21 11.2-481 12/91 15 11.3-32 7/82 .Original 11.2-49 7/82 Original 11.3-33 6/85 3 11.2-50 7/82 Original 11.3-34 7/82 Original 11.2-51 12/91 15 11.3-35 7/82 Original 11.2-52 7/82 Original 11.3-36 7/82 Original 11.2-53 7/82 Original 11.3-37 7/82 Original 11.2-54 7/82 Original 11.3-38 7/82 Original 11.2-55 7/82 Original 11.3-39 12/91 15 11.2-56 7/82 Original 11.3-40 12/91 15 11.2-57 12/94 23 11.3-41 8/93 20 11.2-58 12/91 15 Figure 11.3-1 7/82 Original 11.2-59 12/91 15 Figure 11.3-2 7/82 Original 11.2-60 7/82 Original llA-i 7/82 Original 11.2-61 12/91 15 llA-ii 7/82 Blank Figure 11.2-1 3/94 21 llA-iii 6/83 1 Figure 11.2-2 3/94 21 llA-iv 6/83 1 Figure 11.2-3 3/94 21 llA-v 6/83 1 Figure 11.2-4 12/91 15 llA-1 12/91 15 Figure 11.2-5 12/91 15 llA-2 7/82 Blank Figure 11.2-6 7/82 Original llA-3 4/91 13 Figure 11.2-7 3/94 21 llA-4 6/83 1 Figure 11.2-8 10/95 24 llA-5 6/83 1 Figure 11.2-9 12/91 15 llA-6 6/83 Blank Figure 11.2-10 12/91 15 llA-7 2/93 19 Figure 11.2-11 12/91 15 llA-8 7/82 Blank 11.3-1 12/94 23 llA-9 6/83 1 11.3-2 7/82 Original llA-10 6/83 1 11.3-3 7/82 Original llA-11 6/83 1 11.3-4 7/82 Original llA-12 6/83 1 11.3-5 7/82 Original llA-13 4/91 13 11.3-6 7/82 Original llA-14 7/82 Original

11. 3-7 8/93 20 llA-15 4/91 13 11.3-8 2/93 19 llA-16 4/91 13 11.3-9 7/82 Original llA-17 4/91 13 11.3-10 7/82 Original llA-18 4/91 13 11.3-11 3/94 21 llA-19 4/91 . 13 11.3-12 8/93 20 llA-20 4/91 13 11.3-13 8/93 20 llA-21 6/83 1 11.3-14 3/94 21 llA-22 2/93 19 11.3-14a 10;95* 24 llA-23 4/91 13 11.3-15 3/94 21 llA-24 4/91 13 11.3-16 3/94 21 llA-25 4/91 13 11.3-17 8/93 20 . llA-26 4/91 13 11.3-18 10/95 24 llA-27 6/83 1 11.3-19 3/94 21 llA-28 6/83 1 11.3-20 6/83 1 llA-29 6/83 1 llA-30 6/83 1 11.3-21 10/95 24

.11.3-22 2/93 19 llA-31 6/83 1 ll.3-22a 3/92 16 llA-32 6/83 1 11.3-22b 3/92 16 11.3-23 7/82 Original Cbsl.l2t~;i;: 12 11.3-24 4/91 13 13 11.3-25 4/91 12-i 12/94 23

REVISION 24 10/95 SPS UFSAR LEP-18 L:1:&f Ql BllBCf:l:lZB 21.Sill!

~

12.1-1 12.1-2 J2.All VOLUME IV (continued) 12/94 12/94 Reyiaion 23 23 R..Lsa 13.4-3 13 .4-4

13. 5-1 13.5-2

.12..11..U.

7/82 7/82 7/82 7/82 Reviaion Original Original Original Original 12.2-1 12/94 23 13.5-3 7/82 Original 12.2-2 .12/94 23 13. 5-4 7/82 Original 12.2-3 12/94 23 13 .5-5 7/82 Original 12.2-4 12/94 23 13.5-6 7/82 Original 12.2-5 12/94 23 13.5-7 7/82 Original 12.3-1 12/94 23 13.5-8 7/82 Original 12 .3-2 12/94 23 13.5-9 7/82 Original 12.4-1 12/94 23 13.5-10 7/82 Original 12.5-1 12/94 23 13. 5-11 7/82 Original 12.5-2 12/94 23 13.5-12 7/82 Original 12.6-1 12/94 23 13 .5-13 7 /82 Original 12.7-1 12/94 23 13.5-14 7/82 Original 12.8-1 12/94 23 13.5-15 7/82 Original 12.8-2 12/94 23 13. 5-16 7/82 Original 13.5-17 7/82 Original

!:bs1.12t§;r;: l3 13.5-18 7/82 Original

13. 5-19 7/82 Original 13-i 7/82 Original 13.5-20 7/82* Original 13-ii 7/82 Original 13.5-21 7/82 Original 13-iii 7/82 Original 13.5-22 7/82 Original 13 .1-1 7/82 original 13.5-23 7/82 Original 13.1-2 7/82 Original 13.5-24 7 /82

• Original 13 .1-3 7/82 Original 13. 5-25 7/82

• Original 13 .1-4 7/82 Original 13 .5-26 7/82 Original 13 .1-5 7/82 Original 13.1-6 7/82 Original 13 .1-7 7/82 Original VOLUME V 13 .1-8 7/82 Original 13 .1-9 7/82 Original  !:bs1.I2t§:t: 14 13 .1-10 7/82 Original 13 .1-11 7/82 Original 14-i 8/89 8 13 .1-12 7/82 Original 14-ii 10/92

• 18 13 .1-13 7/82 Original 14-iia 10/92 18 13.1-14 7/82 Original 14-iii 10/95 24 13 .2-1 7/82 Original 14-iv 4/91 13 13 .2-2 7/82 Original 14-v 4/91 13 13.2-3 7/82 Original 14-vi 10/95 24 13 .2-4 7/82 Original 14-vii .10/95 24 13.2-5 7/82 Original 14-viii 12/94 23 13.3-1 7/82 Original 14-ix 12/94 23

13. 3-2 7/82 Original 14-x 7/82 Original 13.3-3 7/82 Original 14-xi 10/92 18 13.3-4 7/82 Original 14-xia 10/92 18 13.3-5 7/82 Original 14-xii 4/91 13 13.3-6 7/82 Original 14-xiii 2/93 19 13.3-7 7/82 original 14-xiv 2/93 19 13.3-8 7/82 Blank 14-xv 2/93 19 13.3-9 7/82 Original 14-xvi 7/82 Original 13 .3-10 7/82 Original 14-xvii 12/94 23 13 .3-11 7/82 Original 14-xviii 12/94 23 13.3-12 7/82 original 14-xix 12/94 23 13.3-13 7/82 original 14-xx 3/94 21 13.3-14 7/82 Original 14.1-1 7/82 Original 13.4-1 7/82 Original 14.1-2 10/95 24 13.4-2 7/82 Original 14.1-3 10/95 24

REVISION 24 10/95 SPS UFSAR LEP-19 LIS'!' QP EPPEC'l'+YI PAGES

• ~

14.2-1 14.2-2

.12.A.t.Jl VOLUME V (continued) 7/82 7/82 10/95 Rayi1ion Original Original 24 h.sl.9.

14.2-50 14.2-51 14.2-52 14.2-53 14.2-54

.la...U.

12/94 12/94 7/82 7/82 4/91 B@Yi1ion 23 23 Original Original 13 14.2-3 14.2-3a 8/89 8 14.2-55 7/82 Original 14 .2-4 8/89 8 14.2-56 3/94 21 14.2-5 3/94 21 14.2-56a 6/90 9 14.2-6 4/91 13 14.2-57 2/93 19 14.2-7 4/91 13 14.2-57a 2/93 19 14.2-8 4/91 13 14.2-58 10/95 24 14.2-9 3/94 21 14.2-59 10/95 24 14.2-10 8/90 10 14.2-60 10/95 24 14.2-11 3/94 21 14.2-61 10/95 24 14.2-lla 8/93 20 14.2-62 10/92 18 14.2-12 3/92 16 14.2-63 2/93 19 14.2-13 3/94 21 14.2-63a 2/93 19 14.2-14 3/94 21 14.2-64 2/93 19 14.2-15 3/94 21 14.2-65 7 /82 Original 14.2-16 3/92 16 14.2-66 3/94 21 14.2-17 6/92 17 14.2-67 3/92 16 14.2-18 6/92 17 14.2-68 2/93 19 14.2-19 6/92 17 14.2-68a 10/95 24.

14.2-20 3/94 21 14.2-69 3/92 16 14.2-20a 3/94 21 14.2-:70 12/94 23 14.2-21 6/92 17 14.2-71 2/93 .19 14.2-22 7/82 Original Figure 14.2-1 8/89 8.

14.2-23 7/82 Original Figure 14.2-2 . 7/82 Original 14.2-24 7/82 Original Figure 14.2-3 8/89 8.

14.2-25 7/82 Original Figure 14.2-4 8/89 8 14.2-26 7/82 Original Figure 14.2-5 7/82 Original 14.2-27 7/82 Original Figure 14.2-6 7/82 Original 14.2-28 7/82 Original Figure 14.2-7 7/82 Original 14.2-29 7/82 Original Figure 14.2-8 7/82 Original 14.2-30 4/91 13 Figure 14.2-9 7/82 Original 14.2-31 10/92 18 Figure 14.2-10 8/90 10 14.2-32 3/94 21 Figure 14.2-11 7/82 Original 14.2-32a 10/92 18 Figure 14.2-12 7 /82 Original 14.2-32b 10/92 18 Figure 14.2-13a* 8/90 10 14.2-33 10/92 18 Figure 14.2-13b 8/90 10 14.2-34 10/92 18 Figure 14.2-13c 8/90 10 14.2-35 7/82 Original Figure 14.2-14 8/90 10 14.2-36 3/94 21 Figure 14.2-15 8/90

• 10 14.2-37 3/94 21 Figure 14.2-16 3/94 21 14.2-37a 3/94 21 Figure 14.2-17 3/94 21 14.2-38 3/94 21 Figure 14.2-18 3/92 15 14.2-39 4/91 13 Figure 14.2-19 3/92 16 14.2-40 4/91 13 Figure 14.2-20 7/82 Original 14.2-40a 3/94 21 Figure 14.2-21 7/82 original 14.2-40b 3/94 21 Figure 14.2-22 7/82 Original 14.2-41 4/91 13 Figure 14.2-23 7/82 Original 14.2-42 4/91 13 Figure 14.2-24 7/82 Original 14.2-43 12/94 23 Figure 14.2-25 7/82 Original

• 14.2-44 12/94 23 Figure 14.2-26a 10/92 18 14.2-45 12/94 23 Figure 14.2-26b 10/92 18 14.2-46 10/95 24 Figure 14.2-26c 10/92 18 14.2-47 12/94 23 Figure 14.2-26d 10/92 18 14.2-48 12/94 23 Figure 14.2-26e 10/92 18 ~

14.2-49 12/94 23 Figure 14.2-26f 10/92 18

REVISION 24 10/95 SPS UFSAR LEP-20 LXS'l' OP EPPEC'l'XYI PAGES

.2..A..sL9.

VOLUME V (continued)

Figure 14.2-27a Figure 14.2-27b 12.lli 10/92 10/92 10/92 Rayipion 18 18

.P..A.a.

Figure 14.2-96 Figure 14.2-97 Figure 14.2-98 Figure 14.2-99 Figure 14.2-100 J2.A.ll 7 /82 7/82 7/82 3/88 3/88 B*viaiop.

Original Original Original 7

.7 Figure 14.2-27c 18 Figure 14.2-27d 10/92 18 Figure 14.2-101 3/88 7 Figure 14.2-27e 10/92 18 Figure 14.2-102 3/88 7 Figure 14.2-27f 10/92 18 Figure 14.2-103 2/93 19 Figure 14.2-28 10/92 18 Figure 14.2-103a 2/93 19 Figure 14.2-29 10/92 18 Figure 14.2-104 2/93 19 Figure 14.2-30 7/82 *original 14.3-1 7/82 Original Figure 14 .2-31 7/82 Original 14.3-2 7/82 Original Figure 14.2-32 7/82 original 14 .3-3 7/82 Original Figure 14.2-33 7/82 Original 14.3-4 7/82 Original Figure 14.2-34 7/82 Original 14.3-5 6/85 3 Figure 14.2-35 7/82 Original 14.3-6 7/82 Original Figure 14.2-36 7/82 Original 14.3-7 7/82 Original Figure 14.2-37 7/82 Original 14 .3-8 7/82 Original Figure 14.2-38 4/91 13 14.3-9 6/85 3 Figure 14.2-39 7/82 /

Original 14.3-10 6/85 3 Figure 14.2-40 7/82 Original 14.3-11 6/85 3 Figure 14.2-41 7/82 Original 14.3-12 6/85 3 Figure 14.2-42 7/82 Original 14.3-13 6/85 3 Figure 14.2-43 7/82 Original 14.3-14 6/85 3 Figure 14.2-44 7/82 original 14.3-15 6/85 3 Figure 14.2-45 7/82 Original 14.3-16 4/91 13 Figure 14.2-46 7/82 Original 14.3-16a 4/91 13 Figure 14.2-47 7/82 Original 14.3-17 6/85 3 Figure 14.2-48 7/82 Original 14.3-18 6/85 3 Figure 14.2-49 7/82 Original 14.3-19 6/85 3 Figure 14.2-50 7/82 Original 14.3-20 6/85 3 Figure 14.2-51 7/82 Original 14.3-21 4/91 13 Figure 14.2-52 7/82 Original 14.3-22 4/91 13 Figure 14.2-53 7/82 Original 14.3-23 10/95 24 Figure 14.2-54 7/82 Original 14.3-24 2/93 19 Figure 14.2-55 7/82 Original 14.3-25 4/91 13 Figure 14.2-56 7/82 Original 14.3-26 10/95 24 Figure 14.2-57 7/82 Original 14. 3-27 10/95 24 Figure 14.2-57a 4/91 13 14.3-27a 10/95 24 Figure 14.2-58 7/82 Original 14.3-28 4/91 13 Figure 14.2-58a 4/91 13 14.3-29 4/91 13 Figure 14.2-59 2/93 19 14.3-30 4/91 13 Figure 14.2-60 2/93 19 14.3-31 10/95 24 Figure 14.2-61 2/93 19 14.3-32 10/95 24 Figure 14.2-62 2/93 19 14.3-33 10/95 24 Figures 14.2-63.through 14.2-83 14 .3-34 4/91 13 Deleted in Revision 19 dated 2/93 14.3-35 4/91 13 Figure 14.2-84 7/82 Original 14.3-36 4/91 13 Figure 14.2-85 7/82 Original 14.3-36a 10/95 24 Figure 14.2-86 7/82 Original 14.3-37 7/82 Originai Figure 14.2-87 7/82 Original 14.3-38 6/85 3 Figure 14.2-88 7/82 Original 14.3-39 6/85 3 Figure 14.2-89 7/82 original 14.3-40 10/95 24 Figure 14.2-90 Figure 14.2-91 Figure 14.2-92 Figure 14.2-93 Figure 14.2-94 Figure 14.2-95 7/82 7/82 7/82 7/82 7 /82 7/82 Original Original

.original Original Original Original Figure 14.3-1 Figure 14.3-2 Figure 14. 3-3 Figure 14.3-4 Figure 14.3-5 Figure 14.3-6 7/82 7/82 7/82 7/82 7/82 4/91 Original Original Original Original*

Original 13 J

REVISION 24 10/95 SPS UFSAR LEP-21 L:Z:&2: Ql llllC2::Z:ltl PAGI&

• .P.AJa Figure 14.3-7 Figure 14.3-8 J2.JlU VOLUME V (continued) 4/91 6/85 Revision 13 3

bJU.

14. 5-llh 14.5-12 14.5-13 14.5-14

.12.A.U.

10/95 2/93 2/93 2/93 Revision 24 19 19 19 Figure 14.3-9 6/85 3 14.5-15 2/93 19 Figure 14.3-10 6/85 3 14.5-16 2/93 19 Figure 14.3-11 6/85 3 14.5-17 2/93 19 Figure 14.3-lla 6/85 3 14.5-18 2/93 19 Figure 14.3-llb 6/85 3 14.5-19 2/93 19 Figure 14.3-12 10/95 24 14.5-20 2/93 19 Figure 14.3-13 10/95 24 14.5-21 2/93 19 Figure 14.3-14 10/95 24 14.5-22 10/95 24 Figure 14.3-15 10/95 24 14.5-23 2/93 19 Figure 14.3-16 4/91 13 14.5-24 2/93 19 Figures 14.3-17 through 14.3-22 14.5-25 2/93 .*19 deleted in Revision 19 dated 2/93 14.5-26 2/93 19 14.4-1 7/82 Original 14.5-27 2/93 19 14.4-2 7/82 Original 14.5-28 10/95 24 14.4-3 6/91 14 14.5-29 12/94 23 14.4-4 10/95 24 14.5-30 12/94 .. 23 14.4-5 10/95 24 14.5-31 2/93 19 14.4-:-6 10/95 24 14.5-32 10/95 24 14.4-6a 12/91 15 14.5-33 12/94 23 14.4-7 12/91 15 14.5-34 12/94 23 12/94 23 14.4-8 7/82 Original 14.5-35 14.4-9 6/85 3 14.5-36 12/94 23 14.4-10 12/91 15 14.5-37 10/95 24 14.4-11 6/85 3 14. 5-38 12/94 23 14.4-12 6/85 3 14.5-38a 12/94 23 14.4-13 7/82 Original 14.5-39 2/93 19 14.4-14 7/82 Original 14.5-40 2/93 19 14.4-15 6/85 3 14.5-41 2/93 19 14.4-16 12/91 15 14.5~42

• 2/93 19 14.4-17 10/95 24 14.5-43 2/93 19 14.4-18 6/91 14 14.5.:..44 10/95 24 14.4-19 6/85 3 14.5-45 3/94 21 14.4-20 7/82 Original 14.5-46 10/95 . 24 14.5-1 10/95 24 Figure 14.5 12/94 23 14.5-2 12/94 23 Figure 14.5-2a 12/94 23 14.5-3 12/94 23 Figure 14.5-2b 12/94 23 14.5-4 12/94 23 Figure 14.5-3a 12/94 23 14.5-5 12/94 23 Figure 14.5-3b 12/94 23 14.5-6 12/94 -23 Figure 14.5-4a 12/94 23 14.5-7 12/94 23 Figure 14.5-4b 12/94 23 14.5-7a 12/94 23 Figure 14.5-5a 12/94 23 14.5-7b 12/94 23 Figure 14.5-5b 12/94 23 14.5-7c 10/95 24 Figure 14.5-6a 12/94 23 14.5-8 12/94 23 Figure 14.5-6b 12/94 23 14.5-9 12/94 23 Figure 14.5-7a 12/94 23 14.5-10 12/94 23 Figure 14.5-7b 12/94 23 14 .5-11 10/95 24 Figure 14.5-8a 12/94 23 14.5-lla 10/95 24 Fi~~e 14.5-8b 12/94 23 14.5-llaa 10/95 24 Figure 14.5-9a 12/94 23 14.5-llb 3/94 21 Figure 14.5-9b 12/94 23

14. 5_-llc 3/94 21 Figure 14.5-lOa 12/94 23 14.5-lld 3/94 21 Figure 14.5-lOb 12/94 23

14. 5-lle 3/94 21 Figure 14.5-lla 12/94 23 14.5-llf 10/95 24 Figure 14.5-llb 12/94 23 .

14.5-llg 10/95 24 Figure 14.5-12a 12/94 23.

REVISION 24 10/95* SPS UFSAR LEP-22 \

1tr1c:ciu :ea.a1s L:tS:C Ql

~ Ja.u Reyiaion -~ ~ B*Yi*ion VOLUME V (continued) 14A-8 7/82 Blank 14A-9 7/82 Original Figure 14.S-12b 12/94 23 14B-i 7 /82 Original Figure 14.5-13a 12/94 23 14B-ii 7/82 Blank Figure 14 .S-13b 12/94 23 14B-iii 7/82 Original Figure 14.S-14a 12/94 23 14B-iv 7/82 Original Figure 14.5-14b 12/94 23 14B-v 7/82 Original Figure 14.5-15a 12/94 23 14B-vi 7 /82 Original Figure 14.5-15b 12/94 23 14B-vii 7 /82

• Original Figure 14.5-16a 12/94 23 14B-l 7/82 Original Figure 14.5-16b 12/94 23 14B-2 7/82 Original Figure 14.5-17a 12/94 23 14B-3 7/82 Original Figure 14.5-17b 12/94 23 14B-4 7 /82 Original Figure 14.5-18a 12/94 23 14B-5 7/82 Original Figure 14.5-18b 12/94 23 14B-6 7/82 Original Figure 14.5-19 3/94 21 14B-7 7/82 Original Figure 14.5-20 3/94 21 14B-8 7/82 Original Figure 14.5-21 3/94 21 14B-9 7/82 Original Figure 14.5-22a 3/94 21 14B-10 7/82 Original Figure 14.5-22b 3/94 21 14B-ll 7/82 Original Figure 14.5-22c 3/94 21 14B-12 3/92 *16 Figure 14.5-22d 3/94 21 14B-13

• 3/92 16 Figure 14.5-23a 3/94 21 14B-14 7/82 Original Figure 14.5-23b 3/94 21 14B-15 7/82 Original Figure 14.5-23c 3/94 21 14B-16 7/82 Original Figure 14.5-23d 3/94 21 14B-17 7/82 Original Figure 14.5-24a 3/94 21 14B-18 7/82 Original Figure 14.5.;.24b 3/94 21 14B-19 7/82 Original Figure 14.5-24c 3/94 21 14B-20 7/82 Original

. Figure 14.5-24d 3/94 21 14B-21 7/82 Original Figure 14.5-25a 3/94 21 14B-22 7/82 Blank Figure 14.5-25b 3/94 21 14B-23 7/82 Original Figure 14.5-25c 3/94 21 14B-24 7/82 Original Figure 14.5-25d 3/94 21 14B-25 7/82 Original Figure 14.5-26a 3/94 21 14B-26 7/82 Original Figure 14.5-26b 3/94 21 14B-27 7/82 Original Figure 14.5-26c 3/94 21 14B-28 7/82 Original Figure 14.5-26d 3/94 21 14B-29 2/93 19 Figure 14.5-27a 3/94 21 14B-30 2/93 19 Figure 14.5-27b 3/94 21 14B-31 2/93 19 Figure 14.5-27c 3/94 21 14B-3la 2/93 19 Figure 14.5-27d 3/94 21 14B-32 7/82 Original Figure 14.5-28a 3/94 21 14B-33 7/82 Original Figure 14.5-28b 3/94 21 14B-34 7/82 Original Figure 14.5-28c 3/94 21* 14B-35 7/82 Original Figure 14.5-28d 3/94 21 14B-36 7/82 Original Figure 14.5-29 3/94 21 14B-37 3/94 21 Figure 14.5-30 3/94 21 14B-37a

• 3/94

• 21 14A-i 7/82 Original 14B-38 7/82 Original.

14A-ii 7/82 Blank 14B-39 7/82 Originai 14A-iii 7/82 Original 14B-40 7/82 Original 14A-iv 7/82 Original 14B-41 7/82 Original 14A-l 7/82 Original 14B-42 7/82 Original 14A-2 7/82 Blank 14B-43 7/82 . Original 14A-3 7/82 Original 14B-44 7/82 Original 14A-4 7/82 Blank 14B-45 3/94 21 14A-5 7/82 Original 14B-46 7/82 Blank 14A-6 7/82 Original 14B-47 7/82 Original 14A-7 7/82 Original 14B-48 7/82 Original

REVISION 24 10/95- SPS UFSAR LEP-23 L:Ci:t Ql lllliC:t:CXl!i i!A~li

• .i..A:.5a.

14B-49 14B-50

~

VOLUME V (continued 7/82 7/82 Rayipion Original Original bSUl.

Figure 15.1-2 Figure 15.1-3 Figure 15.1-4 Figure 15.1-5

~

12/94 3/94 3/94 3/94 Rayiaion 23 21 21 21 14B-51 7/82 Original Figure 15.1-6 3/94 21 14B-52 7/82 Original Figure 15.1-7 3/94 21 14B-53 7/82 Original Figure 15.1-8 3/94 21 14B 7/82 Original Figure 15.1-9 3/94 21 14B-55 7/82 Original Figure 15.1-10 3/94 21 14B-56 7/82 Original Figure 15.1-11 3/94 21 14B-57 7/82 Original Figure 15.1-12 3/94 21 14B-58 7/82 Original Figure 15.1-13 3/94 21 -

14B-59 7/82 Original Figure 15.1-14 3/94 21 14B-60 7/82 Original Figure 15.1-15 3/94 21 14B-61 7/82 Original Figure 15.1-16 3/94 21 14B-62 7/82 Original 15.2-1 7/82 Original 14B-63 7/82 Original 15.2-2 7/82 Original 14B-64 7/82 Original 15.2-3 7/82 Original 14B-65 7/82 Original 15.2-4 7/82 Original 14B-66 7/82 Original 15.2-5 7/82 Original Figure 14B-l 7/82 Original 15.2-6 7/82 Original Figure 14B-2 7/82 Original 15.2-7 7/82 Original Figure 14B-3 7/82 Original 15.2-8 7/82 Original Figure 14B-4 7/82 Original 15.2-9 3/92 16 Figure 14B-5 7/82 Original 15.2-10 7/82 Blank

• Figure 14B-6 7/82 Original 15.2-11 7/82 Original Figure 14B-7 7/82 Original 15.2-12 7/82 Original Figure 14B-8 7/82 Original 15.2-13 7/82 Original Figure 14B-9 7 /82 Original 15.2-14 12/94 23 Figure 14B-10 7 /82 Original 15.2-15 7/82 Original Figure 14B-11 7/82 Original 15.2-16 4/91 13 Figure i4B-12 7/82 Original 15.2-17 7/82 Original Figure 14B-13 7 /82 Original 15.2-18 7/82 .. Original Figure 14B-14 7/82 Original 15.2-19 7/82 Original Figure 14B-15 7 /82 Original 15.2-20 7/82 Original Figure 14B-16 7/82 Original 15.2-21 3/92 16 Figure 14B-17 7/82 Original 15.2-22 6/83 1 Figure 14B 7/82 Original 15.2-23 7/82 Original Figure 14B-19 7/82 Original 15.2-24 2/93 19 Figure 14B-20 7 /82 Original 15.2-25 7/82 Original Figure 14B-21 7 /82 Original 15.2-26 7/82 Original Figure 14B-22 7/82 Original 15.2-27 12/94 23 Figure 14B-23 6/85 3 15.2-28 7/82 Original 15.2-29 7/82 Original 15.2-30 7/82 Original VOLUME VI 15.2-31 6/90 9 15.2-32 7/82 Original

~bia~t!ilt: 15 15.2-33 7/82 Original 15.2-34 6/86 4 15-i 7/82 Original 15.2-35 6/86 4 15-ii 7/82 original 15.3-:1 7/82 Original 15-iii 7/82 Original 15.3-2 7/82 Original 15 .3-3 7/82 Original 15-iv 7/82 Original 15-v 8/89 8 15.4-1 7/82 Original 15-vi 7/82 Original 15.4-2 7/82 Original 15-vii 7/82 Original 15.4-3 7/82 Original i 15.4-4 7/82 Original ' I 15-viii 6/84 2 15.1-1 8/89 8 15.4-5 15.4-6 7/82 7/82 Original Original Figure 15.1-1 7/82 Original

REVISION 24 10/95 SPS UFSAR LEP-24 i.:z:si Ql Bl:!BCil:2:B 2a.a1s

~

15.4-7 15.4-8 12.All VOLUME VI (continued) 7/82 7/82 B*viaion Original Original

.b..sl..9.

15 .5-13 15.5-14 15.5-15

• 15. 5-16 12.A...t.9.

7/82 7 /82 7/82 7/82 B*viaion Original Original Original Original 15.4-9 7/82 Original 15.5-17 7/82 Original 15.4-10 7/82 Original 15.5-18 7/82 Original

.15.4-11 7/82 Original 15.5-19 7/82 Original 15.4-12 7/82 Original 15.5-20 7/82 Original 15 .4-13 7/82 Original 15.5-21 7/82 Original 15.4-14 7/82 Original 15.5-22 7/82 Original 15.4-15 7/82 Original 15.5-23 7/82 Original 15.4-16 7/82 Original 15.5-24 7/82 Original 15.4-17 7/82 original 15.5-25 7/82 -Original 15.4-18 7/82 Original 15.5-26 8/89 .8 15.4-19 7/82 Original 15.5-27 7/82 Original 15.4-20 7/82 Original 15.5-28 7/82 Original 15.4-21 7/82 Original 15.5-29 7/82 Original 15.4-22 7/82 Original 15.5-30 7/82 Original 15.4-23 7/82 Original 15.5-31 7/82 Original 15 .4-24 7/82 Original 15.5-32 7/82 Original 15.4-25 7/82 Original 15.5-33 7/82 Original 15.4-26 7 /82 original 15.5-34 7/82 Original 15.4-27 7/82 Original 15.5-35 7/82 Original 15.4-28 7/82 Original 15.5-36 7/82 Original 15.4-29 7/82 Original 15.5-37 7/82 Original 15.4-30 7/82 original 15.5-38 7/82 Original 15.4-31 7/82 Original 15.5-39 7/82 Original 15.4-32 7/82 Original 15.5-40 12/91 15 15.4-33 7/82 Original 15.5-41 7/82 Original 15.4-34 7/82 Original 15.5-42 7/82 Original 15.4-35 7/82 Original 15.5-43 7/82 Original 15.4-36 7/82 Original 15.5-44 7/82 Original 15.4-37 7/82 Original 15.5-45 7/82 Original 15.4-38 7/82 Original 15.5-46 8/89 8 15.4-39 7/82 Original 15.5-47 8/89 8 15.4-40 7/82 Original 15.5-48 8/89 8 15.4-41 7/82 Original 15.5-49 6/91 14 15.4-42 7/82 Original 15.5-50 7/82 Original 15.4-43 7/82 Original 15.5-51 7/82 Original 15.4-44 7/82 Original 15.5-52 7/82 Original 15.4-45 7/82 original 15.5-53 7/82 Original Figure 15.4-1 7/82 Original 15.5-54 7/82 .Original Figure 15.4-2 7/82 Original 15.5-55 7/82 Original Figure 15.4-3 15.5-56 7/82 Original (Sheet 1) 7/82 Original 15.5-57 7/82 Original (Sheet 2) 7/82 Original 15.5-58 7/82 Blank (Sheet 3) 7/82 original 15.5-59 7/82 Original 15.5-1 7/82 Original 15.5-60 7/82 Original 15.5-2 7/82 Original 15.5-61 7/82 Original 15.5-3 7/82 Original 15.5-62 7/82 Originai 15.5-4 7/82 Original 15.5-63 7/82 Original 15.5-5 7/82 Original Figure 15.5-1 3/94 21 Original 15.5-6 7/82 original Figure 15.5-2 7/82 15.5-7 7/82 Original Figure 15.5-3 7/82 Original 15.5-8 7/82 Original Figure 15.5-4 7/82 Original 15.5-9 7/82 Ori9inal Figure 15.5-5 7/82 Original 15.5-10 7/82 - Original Figure 15.5-6 7/82 Original*

15. 5-11 7/82 original Figure 15.5-7 7/82 Original 15.5-12 7/82 Original Figure 15.5-8 7/82 Original

REVISION 24 10;95* SPS UFSAR LEP-25 LJ:l:C QI: 11:1:IC:CJ:JZI 2li~II

• E...IUa Figure 15.5-9 Figure 15.5-10 uu VOLUME VI (continued) 7/82 7/82 Rayiaion Original Original

~

15A-12a 15A-12b 15A-13 15A-14 J2.JLt...9.

8/89 6/91 8/89 8/89 8/89 Reyiaion 8

14 8

8 8

Figure 15.5-11 7/82 Original 15A-15 Figure 15.5-12 7/82 Original 15A-16 8/89 8 Figure 15.5-13 7/82 Original 15A-16a 8/89 8 Figure 15.5-14 7/82 Original 15A-16b 8/89 8 Figure 15.5-15 7/82 Original 15A-17 8/89 8 Figure 15.5-16 7/82 Original 15A-18 8/89 8 Figure 15.5-17 6/84 2 15A-19 7/82 Original Figure 15.5-18 6/84 2 15A-20 12/94 23 Figure 15.5-19 6/84 2 15A-21 12/94 23 15.6-1 7/82 Original 15A-21a 12/94 23 15.6-2 7/82 Original 15A-22 12/94 23 15.6-3 4/91 13 15A-23 8/89 8 15.6-4 8/89 8 15A-24 8/89 8 15.6-4a 8/89 8 15A-25 7/82 Original 15.6-4b 8/89 8 15A-26 6/91 14 15.6-5 8/89 8 15A-27 8/89 8 15.6-5a 8/89 8 15A-28 7/82 Original 15.6-6 8/89 8 15A-29 8/89 8 15.6-6a 8/89 8 15A-30 7/82 Original

. 15. 6-7 8/89 8 15A-31 7/82 Original 15.6-8 8/89 8 15A-32 8/89 8 15.6-9 8/89 8 15A-33 8/89 8 15.6-10 7/82 Original 15A-33a 8/89 8

15. 6-11 8/89 8 15A-34 12/94 23 15.6-12 8/89 8 15A-35 7/82 Original 15.6-13 8/89 8 15A-36 4/91 13 15.6-14 3/92 16 15A-37 4/91 13 15.6-15 7/82 Original 15A-38 7/82 Original 15.6-16 7/82 Original 15A-39 7/82 Original 15.6-17 7/82 Original 15A-40 7/82 Original Figure 15.6-1 7/82 Original 15A-41 7/82 Original Figure 15.6-2 10/92 18 15A-42 6/91 14

'Figure 15.6-3 3/88 7 15A-43 8/89 8 Figure 15.6-4 3/88 7 15A-44 8/89 8 15.7-1 7/82 .original Figure 15A-1 7/82 Original 15.7-2 6/83 1 Figure 15A-2 . 7/82 Original 15.7-3 6/83 1 Figure 15A-3 7/82 Original 15A-i 7/82 Original Figure 15A-4 7/82 Original 15A-ii 7/82 Blank Figure 15A-5 7/82 Original 15A-iii 6/91 14 Figure 15A-6 7/82 Original 15A-iv 7/82 Original Figure 15A-7 7/82 Original 15A-v 8/89 8* Figure 15A-8 7/82 Original 15A-vi 7/82 Original 15A-1 7/82 Original ~ba:r;it~;i:: 16

.15A-2 7/82 Blank 15A-3 8/89 8. 16-i 2/93 19 15A-4 7/82 Original 16-ii 2/93 19 15A-5 8/89 8 16.1-1 2/93 19 8/89 8 16.2-1 2/93 19 15A-6 15A-7 7/82 Original 16.2-2 2/93 19 15A-8 7/82 Blank 16.2-3 2/93 19 15A-9 7/82 Original 16.2-4 2/93 19 15A-10 6/91 14 16.2-5 2/93 19 15A-11 7/82 Original 16.2-6 2/93 19 ...

15A-12 8/89 8 16.2-7 2/93 19

REVISION 24 10/95 SPS UFSAR LEP-26 LIST OP EPPECT+Yli PAGES

.P.AJa 16.2-8 16.2-9 l2..A.U VOLUME VI (continued) 2/93 2/93 Rayiaion 19 19

.P.AJa 17.2-38 17.2-39 17.2-40 17.2-41 12.ll..9.

12/94 12/94 12/94 12/94 Rayiaion 23 23 23 23 16.2-10 2/93 19 17.2-42 12/94 23 16 .2-11 2/93 19 17.2-43 12/94 23 16.2-12 2/93 19 17.2-44 12/94 23 16.2-13 2/93 19 17.2-45 12/94 23 16.2-14 2/93 19 17.2-46 12/94 23 16.2-15 2/93 19 17.2-47 12/94 23 16.2-16 2/93 19 17.2-48 12/94 23 16.2-17 2/93 19 17.2-49 12/94 23 16.2-18 2/93 19 17.2-50 12/94 23 17.2-51 12/94 23

!:bs!.l2t~;i:: l:Z 17.2-52 12/94 23 17.2-53 12/94 23 17-1 12/91 15 17.2-54 12/94 23 17.2-i 12/94 23 17.2-55 12/94 23 17.2-ii 12/94 23 17.2-56 12/94 23 17.2-iii 12/94 23 17 .2-57 12/94 23 17.2-iv 12/94 23 17.2-58 12/94 23 17.2-v 12/94 23 17.2-59 12/94 23 17.2-1 12/94 23 17.2-60 12/94 23 17.2-2 12/94 23 17.2-61 12/94 23 17.2-3 12/94 23 17.2-62 12/94 23 17.2-4 12/94 23 17.2-63 12/94 23 17.2-5 12/94 23 17 .2-64 12/94 23 17.2-6 12/94 23 17.2-65 12/94 23 17.2-7 12/94 23 17.2-66 12/94 23 17.2-8 12/94 23 17 .2-67 12/94 23 17.2-9 12/94 23 17.2-68 12/94 23 17.2-10 12/94 23 17.2-69 12/94 23 17.2-11 12/94 23 17.2-70 12/94 23 17.2-12 12/94 23 17.2-71 12/94 23 17.2-13 12/94 23 17.2-72 12/94 23 17.2-14 12/94 23 17 .2-73 12/94 23 17.2-15 12/94 23 17.2-74 12/94 23 17.2-16 12/94 23 17 .2-75 12/94 23 17.2-17 12/94 23 *17.2-76 12/94 23 17.2-18 12/94 23 17.2-77 12/94 23 17 .2-19 12/94 23 17.2-78 12/94 23 17.2-20 12/94 23 17.2-79 12/94 23 17.2-21 12/94 23 17.2-80 12/94 23 17.2-22 12/94 23 17.2-81 12/94 . 23 17.2-23 12/94 23 17.2-82 12/94 23 17.2-24 12/94 23 17.2-83 12/94 23 17.2-25 12/94 23 17.2-84 12/94 23 17 .2-26 12/94 23 17.2-85 12/94 23 17.2-27 12/94 23 17.2-86 12/94 23 17.2-28 12/94 23 17.2-87 12/94 23 17.2-29 12/94 23 17.2-88 12/94 23 17.2-30 12/94 23 17.2-89 12/94 23 12/94 23 17.2-31' 12/94 23 17.2-90 17.2-32 12/94 23 17.2-91 12/94 23 17.2-33 12/94 23 17.2-92 12/94 23 17.2-34 12/94 23 17.2-93 12/94 23 17.2-35 12/94 23 17.2-94 12/94 23 17.2-36 12/94 23 17.2-95 12/94 23 17.2-37 12/94 23 17.2-9"6 12/94 23

REVISION 24 10/95 SPS UFSAR LEP-27 LIST OP EFFECTIVE PAGES

• VOLUME VI (continued) 17.2-97 17.2-98 12/94 12/94 Reyi11ion 23 23 Rovi1ion 17.2-99 12/94 23 17.2-100 12/94 23 17.2-101 12/94 23 17.2-102 12/94 23 17.2-103 12/94 23 17.2-104 12/94 23 17.2-105 12/94 23 17.2-106 12/94 23 17.2-107 12/94 23

-REVISIOt-.f 23 12/94 SPS UFSAR VIRGINIA ELECTRIC AND POWER COMPANY OPERATIONAL QUALITY. ASSURANCE PROGRAM TOPICAL REPORT

• VEP-1-5A (UPDATED)

Amendment Five June, 1986 (Updated 2/94)

REVISION 23 12/94 SPS UFSAR TABLE OF CONTENTS Section No, ~

Table of Contents List of Figures

~

17.2-i 17-2-iii List of Tables 17.2-iii List of Amendments 17.2-iv Abstract 17.2-v 17.2 Quality Assurance During the Operations Phase 17.2-1 17.2.0 General 17.2-1

.1 Topical Report 11:2-1

.2 Quality Assurance Standards and Guides 17.2-1 17.2.1 Organization 17.2-3 17.2.1.1 General Description - Organization 17.2-3

.2 Nuclear Management 11.2.:4

.3 Organization 17.2-18 17.2.2 Quality Assurance Program 17.2-19 17.2.2.1 General Description 17.2-19

.2 Quality Assurance Program 17.2-20

.3 Identification of Structures, Systems, and Components 17.2-21

.4 Periodic Review of the Operational Quality Assurance 17.2-21 Program

.5 Qualification of Quality Assurance Department 17.2-21 Personnel

.6 Certification of Quality Assurance Department 17.2-22 Personnel

.7 Certification of Other Support Personnel 17.2-22 17.2-i June, 1986

-=~--=---=~~~~-=-=--~~~~---~-

--=--== ---

.--=--

REVISION 23 12/94 SPS UFSAR Section No. ~ ~

• 17.2.3 17.2.4 17.2.5 Design Control Procurement Document Control Instructions, Procedures, and Drawings 17.2-23 17.2-25 17.2-26 17.2.6 Document Control 17.2-27 17.2.7 Control of Purchased Material, Equipment, and 17.2-28 Services 17.2.8 Identification and Control of Materials, Parts, and 17.2-30 Components 17.2.9 Control of Special Process 17.2-3,1 17.2.10 Inspection 17.2-32 17.2.11 Test Control 17.2-34 17.2.12 Control of Measuring and Test Equipment 17.2-35 17.2.13 Handling, Storage, and Shipping 17.2-36 17.2.14 Inspection, Test, and Operating Status 17.2-37 17.2.15 Nonconforming Materials, Parts, and Components 17.2-38 17.2.16 Corrective Action 17.2-40

.1 Authority to Stop Work 17.2-41

.2 Imposition of "Stop Work" 17.2-41 17.2.17 Quality Assurance Records 17.2-43 17.2.18. Audits 17.2-44

• '.17.2-ii June, 1986

REVISION 23 12/94

• SPS UFSAR LIST OF FIGURES (APPENDIX A) figure No, 17.2.1-1 17.2.1-2 Nuclear Organization Nuclear Station Organization 17.2-47 17.2-48' LIST OF TABLES (APPENDIX B)

Table No, 17.2.0 Conformance of the Company's Operational 17.2-50 Quality Assurance Program to NRC Regulatory Guides and ANSI Standards 17.2.2 Relationship of the Company's Operational 17.2-100 Quality Assurance Program to Appendix B, 10 CFR 50 17.2-iii June, 1986

REVISION 23 12/94 SPS UFSAR

• LIST OF AMENDMENTS

• Amendment Original No. Amendment 07-01-75 Pate One 12-30-75 Two 09-27-76 Three 03-01-77 Four 10-01-82

• Four (Updated) 08-30-85 Five 06-30-86 Five (Updated) 03-23-87 Five (Updated) 06-21-88 Five (Updated) 06-21-89 Five (Updated) 06-21-90 Five (Updated) 06-28-91

• 17.2-iv June, 1986

REVISION 23 12/94 SPS UFSAR ABSTRACT

• This topical report describes Virginia Electric and Power Company's, hereafter referred to as the Company, quality assurance program for the operational phase of its nuclear power stations. The report is organized as, distributed, and used for Chapter 17, part 2 - Quality Assurance (Operations) - of the Company's Updated Final Safety Analysis Reports. The Company quality assurance program conforms to applicable regulatory requirements such as 10 CFR 50, Appendix B and to approved industry standards endorsed therein as clarified within this topical report. Included is a point-by-point comparison of the program with the 18 criteria of 10 CFR 50, Appendix B.

This topical report is intended to be a comprehensive up-to-date description of the Company's Operational Quality Assurance Program for nuclear power generating stations.

The Operational Quality Assurance Program is defined as those managerial and administrative policies and controls used to assure the safe and reliable operation of the nuclear facilities. These include all those planned and systematic actions necessary to provide adequate confidence to management and regulatory agencies that structures, systems, and components will perform satisfactorily in service. The Operational Quality Assurance Program encompasses policies, directives, instructions, training, and procedures which ensure compliance with reguations, Codes, standards, licenses, and other Company commitments. As such, this topical

• report, in conjunction with the applicable operating license, provides the foundation for operating the nuclear facilities in a manner which ensures the safety of the public, employees, and plant equipment. The policies are further defined through the Nuclear Operating Department Standards (NODS), the applicable Safety Analysis Report (SAR), Nuclear Design Control Manual (NDCM), and each facility's emergency plan, physical security plan, radiological protection plan, and* fire protection plan.

Administrative and implementing procedures govern the various aspects of day-to-day operation of the nuclear facilities.

The Company's Operational Quality Assurance Program Topical Report is referred to by several generic titles both within this document and within other administrative controls for each nuclear facility. These include Chapter 17.2 of the UFSAR, the [Company's] quality assurance program, the Operational Quality Assurance Program (upper and lower cased letters), the QA Topical Report, VEP 1-SA, Quality Assurance Program - Operational Phase, etc. These are used interchangeably to refer to this document which represents Management's philosophy and methodologies for complying with the 18 criteria of 10 CFR 50, Appendix B.

17.2-v June, 1986

REVISION 23* 12/94 SPS UFSAR

• 17.2 17.2.0 QUALITY ASSURANCE DURING THE OPERATIONS PHASE General It is the policy of the Company to establish and maintain a formal quality assurance program for the operational phase of nuclear power generating stations.

This program is described by written policies, standards, and procedures. The application of this program accomplishes two important objectives: (1) to provide orderly, uniform administrative and managerial procedures to assure safe, reliable, and economic operation of nuclear power stations and (2) to assure compliance with regulations promulgated by the U.S. Nuclear Regulatory Commission.

17.2.0.1 Topical Report This topical report is written in the format of a Safety Analysis Report (SAR)

Chapter 17, part 2, "Quality Assurance During the Operations Phase", in accordance

• with the NRC's "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants" (Nov. 1975) and subsequent NRC guidelines. The quality assurance program described herein is applicable to all Company nuclear power stations as referenced by Chapter 17 of the stations' UFSARs.

Subsequent changes to the Company's Operational Quality Assurance Program will be incorporated as applicable in this topical report. The topical report is intended to be a comprehensive description of the Company's Operational Quality Assurance Program for nuclear power stations.

17.2.0.2 Quality Assurance Standards and Guides The Company Operational Quality Assurance Program conforms to Appendix B of 10 CFR 50 as amended and complies with the regulatory positions of the Regulatory Guides indicated in table 17.2.0, as modified or clarified in that table .

• 17.2-1 June, 1986

REVISION 23 12/94 SPS UFSAR TABLE 11.2.0 Conformance of the Company's Operational Quality Assurance Program To NRC Regulatotv Guides and ANSI Standards The ANSI standards, and other documents (i.e., other standards, codes, regulations, or appendices)*that are required to be included as a part of this quality assurance program are either identified in Table 17.2.0 or they are described herein.

Although this table includes references to ANSI Standards and Regulatory Guides that are required to be a part of this quality assurance program, the table is not intended to be a complete list of all NRC Regulatory Guides (etc.) to which the Company is committed. The specific applicability or acceptability of these listed standards, codes, regulations, or appendices is either covered in this program or such documents are not considered as quality assurance program requirements; although they may be used as guidance. When sections of ANSI Standards and other documents are referenced within this program, it is understood that the Company will comply with the referenced sections as clarified in Table 17.2.0.

GENERIC STATEMENTS WITH REGARDS TO TABLE 17.2.0 AND THE OPERATIONAL QUALITY ASSURANCE PROGRAM For operations phase maintenance and modification activities which are comparable in nature and extent to similar activities conducted during the construction phase, the Company shall control these. activities under this Operational Quality Assurance Program. Designated modifications may be controlled under a contractor's Quality Assurance Program which has been approved by the Company's Quality Assurance Program.

• When this Operational Quality Assurance Program or an approved contractor's Quality Assurance Program is used, the Company shall comply with the Regulatory Position established in the guides listed herein in that quality assurance programmatic/administrative requirements included therein (subject to the clarification in this table) shall apply to these maintenance and modification activities even though such requirements may not have been in effect originally. Technical requirements associated with the maintenance or modification shall be the original requirements or better (e.g., code requirements, material properties, design margins, manufacturing processes, and inspection requirements).

Defjnjtjons in the referenced standards in this table which are not included in ANSI N45.2.1 O will be used as clarified in the Company's commitment to Regulatory Guide 1.74.

17.2-2 June, 1986

REVISION 23 12/94 SPS UFSAR 17.2.1 ORGANIZATION

• • 17.2.1.1 A.

General Description Nuclear Organization Nuclear is divided into five distinct groups; Nuclear Operations, Nuclear I

Engineering Services, Nuclear Services, Nuclear Administrative Services, and Nuclear Quality Assurance. Nuclear Operations, Nuclear Services, Nuclear Administrative Services, and Nuclear Engineering Services are responsible for licensing, operation, and support of the nuclear power stations. Nuclear Quality Assurance has the responsibility *to monitor compliance with the Operational Quality Assurance Program.

B. Nuclear Operations Nucl~ar Operations is a line organization responsible for operation and maintenance of the Surry and North Anna Nuclear Power Stations. This organization is comprised of various departments, including Operations, Maintenance, Outage & Planning, Nuclear Operations Support, Station Nuclear Safety, Station Emergency Planning, Station Licensing, Station Procedures, Radiological Protection, Chemistry, Safety & Loss Prevention, Station Records Management, and Nuclear Site Services (maintenance support, modifications, and plant improvement projects) .

• c. Nuclear Engjneerjng services Nuclear Engineering Services is the design authority for the Nuclear Organization and provides design and operational engineering support to the nuclear stations. This organization is comprised of departments for .

each engineering discipline, including Nuclear Engineering, Electrical Engineering, Civil/Mechanical Engineering, Nuclear Analysis & Fuels Engineering, lnservice Inspection/Non-Destructive Examination (ISI/NDE)

& Engineering Programs, and Special Projects.

D. Nuclear Services Nuclear Services is an organization responsible for Nuclear Licensing and Programs, Nuclear Business Services, Nuclear Training, Nuclear Materials, and Nuclear Emergency Preparedness.

E. Nuclear Administrative Services The Nuclear Administrative Services Group is responsible for supporf functions associated with* Personnel Administration, Management Information & Planning, Fitness For Duty, and Nuclear Projects .

• 17.2-3

REVISION 23 12/94 SPS UFSAR F. Nuclear Quality Assurance Nuclear Quality Assurance is responsible for independently planning and

• performing activities to verify the development and effective implementation of nuclear management's quality assurance programs for engineering, procurement, construction, modification, maintenance, and operation activities associated with the Nuclear Stations.

17.2.1.2 Nuclear Management I A senior Yice President - Nuclear The Senior Vice President - Nuclear has corporate responsibility for and directs the planning and development of the Nuclear Organization staff, organization resources, and nuclear power generation.

I

1. Management Safety Review Committee (MSRC)

The MSRC is the body which performs the offsite safety review I

function. It reports to the Senior Vice President - Nuclear and provides an independent review in the areas of station operations, maintenance, reactivity management, engineering, chemistry & radiochemistry, radiological safety, quality assurance practices, and emergency preparedness. The. Technical Specifications of each station further define the function, composition, alternates, consultants, meeting frequency, quorum, reviews, audits, authority and records of this committee.

2. Nuclear Oversight Board (NOB)

The NOB functions to provide independent review and oversight of

• I nuclear activities at the senior management level and in an advisory capacity to the Senior Vice President - Nuclear. The NOB reviews nuclear management practices, policy issues, regulatory and performance trends and organizational factors relating to nuclear activities, and provides program oversight through management reports, document reviews, group discussions, and individual experience. Membership consists of senior nuclear utility executives and other members appointed on the basis of industry knowledge and/or expertise.

B. Vice President-Nuctear Operations The Vice President - Nuclear Operations is the Corporate individual responsible to the Senior Vice President - Nuclear for the operation of the nuclear power stations. He has overall responsibility for implementing the quality assurance program for the operational phase of the nuclear power stations.

17.2-4

REVISION 23 12/94 SPS UFSAR

1. Assistant Vice President - Nuclear Operations Responsible to the Vice President - Nuclear Operations and provides assistance in the day-to-day operation of the nuclear power stations.

2. Station Manager Responsible to the Vice President - Nuclear Operations for the overall safe and efficient operation of the station, and for the implementation of quality assurance requirements in the areas specified by the operational quality assurance program. The Station Manager has supervisory control over all Virginia Electric and Power Company personnel within the station organization and administrative control over all other Company and non-Company individuals within the nuclear site's boundary. The Station Manager is the local

. representative of Company management and is empowered to implement all Company policy with regard to operations of the facility, support of Company public relations policy, and employee relations policies. The Station Manager is also responsible for coordinating station functions with offsite (Company and non-Company) agencies and services.

In the absence of the Station Manager, these duties will be assumed by the Assistant Station Manager (Operations & Maintenance) unless otherwise designated in writing.

I

a. Assistant Station Manager <Operations and Maintenance)

Responsible to the Station Manager for directing and coordinating all aspects of day-to-day station operations and maintenance. The Assistant Station Manager Operations and Maintenance (O&M) is the Vice Chairman of the Station Nuclear Safety and Operating Committee (SNSOC) and is responsible for planning and coordination of unit outages. In the absence of the Assistant Station Manager (O&M), the Station Manager assumes the duties of the Assistant Station Manager (O&M). In the absence of both the Station Manager and the Assistant Station Manager (O&M),

these duties will be assumed by the Superintendent - Operations unless otherwise designated in writing.

a 1 Supenntendent-Operations I The Superintendent - Operations reports directly to the Assistant .Station Manager (O&M) and is responsible for directing and coordinating station operations and fuel handling activities in accordance with approved plans, programs, licenses, Technical Specifications, and good operating practices. He is responsible for identifying deviations from the Technical Specifications and Facility Operating License (FOL) and for reporting any unusual occurrences in connection with station operations to the Assistant Station Manager (O&M or NS&W. .

• 17.2-5

REVISION 23 12/94 SPS UFSAR The Superintendent - Operations is also responsible for: 1) development and implementation of uniform operating policies and procedures, 2) implementation of on-the-job training for Operations personnel, 3) ensuring that each shift is adequately staffed and sufficient back-up personnel are available, 4) ensuring that all required operating data is properly recorded and retained as appropriate, and 5) being a participating member of the SNSOC.

a.1.1 Supervisor Shift Operations The Supervisor Shift Operations reports to the Superintendent - Qperations and provides direct supervision to the Shift Supervisors; operational input to the SNSOC, and identifies any deviations from the Technical Specifications or any unusual events.

The Supervisor Shift Operations must possess a valid Senior Reactor Operator (SRO) license, and may only be relieved by an individual who possesses a valid SRO license. This position fulfills the function of the "operations manager" as described in ANS 3.1 (12(19 Draft).

a.1.2 Operations Shift Sut>ervisor The Operations Shift Supervisor directs the operations activities of the station for the assigned shift. He is responsible for maintaining the safe operation of the facility under all conditions and maintaining a broad perspective of the operational conditions affecting the safety of the facility. The Operations Shift Supervisor shall not become totally involved in any single operation when multiple operations are occurring at the facility.

When both units are operating, the Operations Shift Supervisor may have command responsibility for one of the operating units in addition to being responsible for overall command of the facility.

The Operations Shift Supervisor shall perform the initial classification of station deviation reports (e.g.,

• REPORTABLE" or "NON-REPORTABLE"). If any event listed in. the administrative procedure for notification requirements is identified, the Operations Shift

. Supervisor shall notify the Superintendent Operations or the SRO on call.

17.2-6

REVISION 23 12/94 SPS UFSAR The Operations Shift Supervisor must possess a valid SRO lic~nse, and may only be relieved by an indi~idual I

• *who possesses a valid SRO license .

a.1.3 Assjstant Shift Supervisor During two unit operation, Assistant Shift Supervisors (Operations) are normally delegated the command I

responsibility for one of the units and report directly to the Operations Shift Supervisor. The Assistant Shift Supervisor is responsibJe for ensuring that unit operations during his shift are conducted in accordance with the requirements of the Technical Specifications, the currently approved operating procedures, and Company policies which apply to his shift.

The Assistant Shift Supervisor must possess a valid SRO license, and may only be relieved by an individual who possesses a valid SRO license.

I a2 Superintendent Ma;menance I The Superintendent -Maintenance reports directly to the Assistant Station Manager (O&M) and is responsible for directing and coordinating the maintenance activities at the station. He is responsible for: 1) ensuring that station facilities

• and equipment are maintained in accordance with regulatory requirements and station procedures, 2) the development and implementation of uniform policies and procedures for installation, maintenance, and repair of station equipment and systems, 3) ensuring maintenance tasks will be performed in a timely and efficient manner, 4) detailed maintenance planning to support scheduled outages being completed as needed, and 5) participating as a member of the SNSOC.

The Supervisor Electrical Maintenance, Supervisors Mechanical

-Maintenance, Supervisor Instrumentation & Control, Supervisor Maintenance Support, Supervisor Maintenance Engineering, and Quality Maintenance Team (QMT) Coordinator report to the Superintendent Maintenance.

a3 Superintendent Outage & Planning I

.The Superintendent Outage & Planning reports directly to the Assistant Station Manager (O&M). He is responsible for the overall planning and scheduling of maintenance and maintenance-related work activities such that safe and reliable plant operation is optimized. He is also responsible for the execution of outages, maintenance of plant equipment history, and monitoring of station performance.

• 17.2-7

REVISION *23 12/94 SPS UFSAR The Unit Outage Coordinators, Supervisor Daily Plan. ning, and~

Supervisor Scheduling report to the Superintendent Outage &

Planning.

b. Assistant Stat;on Manager (Nuclear Safety and Licensing)

Responsible to the Station Manager for directing and coordinating nuclear safety issues at the station. The Assistant Station Manager (NS&L) is the Chairman of the Station Nuclear_ Safety and Operating Committee (SNSOC) and conducts periodic meetings to ensure compliance with station technical specifications, manage licensing activities within the station, interface with the Manager-Nuclear Licensing and Programs on operating experience and safety and licensing issues, manage station procedures and manage station emergency plan activities. The Assistant Station Manager (NS&L) maintains information on industry operating experience, is cognizant of licensing and regulatory issues, administers the Commitment Tracking System (CTS), is responsible for nuclear safety and the Shift Technical Advisors (STAs), administers the Station Emergency Plan, and ensures adequate training for station employees regarding emergency preparedness.

b.1 Supervisor - Station Nuclear Safety (SNS) I The Supervisor - SNS reports directly to the Assistant Station Manager (NS&L) and is responsible for providing guidance to and monitoring the performance of the Shift Technical Advisors *

(STAs). He is responsible for administration of the station deviation report (DR) program including multidiscipline reviews, reviewing DRs for reportability to the NRC, presentation to SNSOC, and maintenance of the database. The Supervisor -

SNS is also responsible for reviewing DRs for adverse trends and providing periodic trend reports to management, analyzing plant performance following transients or reactor trips, administering the Operation Experience Program,. and implementing the Human Performance Enhancement Program.

b.2 Supervisor - Ucensjng I The Supervisor - Licensing reports directly to the Assistant Station Manager (NS&L) and is responsible for the coordination of licensing activities for the power station to ensure compliance with regulatory requirements. He is responsible for managing the Commitment Tracking System, ensuring that commitments are completed or resolved by the appropriate date, providing interface with regulatory agencies, interfacing with SNS and Corporate Nuclear Licensing and Programs (NL&P), preparing Licensee Event Reports (LERs), presenting LERs to SNSOC, and submitting the LERs to the NRC.

17.2-8

• REVISION 23 12/94 SPS UFSAR b.3 Supervisor - Station Procedures The Supervisor - Station Procedures is responsible to the Assistant Station Manager (NS&L) for the development, review, and approval of technical procedures used at the station and to ensure the technical and editorial accuracy of the procedure generation and revision processes.

b.4 Stat;on Coordinator - Emergency Planning The Station Coordinator - Emergency Planning reports directly to the Assistant Station Manager (NS&L) and is responsible for the administration and coordination of the Station Emergency Plan. He coordinates emergency preparedness activities between station departments, corporate support organizations, local political subdivisions, and emergency response groups.

The Station Coordinator - Emergency Planning also assists in developing and conducting emergency preparedness training programs and emergency drills.

b.5 Station Environmental Compliance Coordinator (ECC)

The Station ECC reports directly to the Assistant Station Manager (NS&L) and is responsible for the administration and coordination of the environmental issues associated with the station. He coordinates environmental protection related activities between station departments and corporate support organizations (Air and Water Quality) and assists in the initial determination of environmental event reportability. The ECC also assists in developing and conducting response training for non--radiological environmental events (e.g., oil spills, hazardous substance spills, etc.).

c. Supenntendent Site services Responsible to the Station Manager for directing all aspects of assigned projects including coordination of activities with station management, engineering, and construction. Support activities such as accounting, procurement planning, scheduling and cost control are also included in these responsibilities.

The Superintendent - Construction, Supervisor - Construction Engineering, Supervisor - Construction Controls, and Supervisor -

Facilities & Support report to the Superintendent Site Services .

• 17.2-9

REVISION 23 12/94 . SPS UFSAR ...

d. Superintendent Radiological Protection Responsible to the Station Manager for administering the Radiological Protection Program at the station. Responsibilities include: 1) monitor the radiological effluent programs and personnel radiation protection programs, 2) maintain records of radiological exposures for all persons working or visiting within the station's restricted area, 3) ensure regular surveys of the station, 4) maintain records of background radiation levels, and 5) check all radioactive material releases and shipments from station and maintain appropriate records. The Radiological Protection group is responsible for determining the radiation levels of all work areas, and posting, as needed, areas where sources of radiation exist.

Additionally, the Superintendent Radiological Protection is also responsible for managing the primary and secondary plant chemistry programs and for coordinating activities related to non-radiological environmental protection.

The Superintendent Radiological Protection directs the activities of his group to minimize the exposure of station personnel to excessive doses of radiation and to prevent the spread -of radioactive contamination. All activities in these areas are coordinated with other station groups to ensure full awareness of problems through implementation of the station ALARA program.

The Superintendent Radwaste (Surry), Supervisor Radiological

• Engineering, Supervisor Health Physics Technical Services, Supervisor Health Physics Operations, and Supervisor Chemistry report to the Superintendent Radiological Protection.

The Superintendent Radiological Protection also participates as a 1*

member of the SNSOC.

e. Supervisor Administrative Services I The Supervisor Administrative *services reports to the Station Manager and is responsible for managing the activities related to administrative tasks for smooth station operation. These tasks include: planning and budget, station records management, station safety and loss preven~ion, fire protection, and medical assistance.

The Business Systems Supervisor, Supervisor Records Management, Supervisor Station Safety & Loss Prevention, and Site - Access In-Process Coordinator report to the Supervisor Administrative Services.

17.2-10

REVISION 23 12/94 SPS UFSAR

- I t Station Supervisory Personnel Responsible directly to the Station Manager through theirl respective superintendents, for implementing the operational quality assurance program requirements applicable to their specific areas of responsibility.

g. Station Staff I It is the responsibility of each member of the station staff to adhere to the provisions contained in the operational quality assurance program when performing their work tasks to assure quality workmanship. Personnel with unescorted access status shall receive training (Nuclear Employee Training) in the use of and adherence to the operational quality assurance program.

h. Station Nuclear Safety and Operating Committee I Serves in an advisory capacity to the Station Manager. The technical specifications of each station define the responsibilities of this committee. The Station Nuclear Safety and Operating Committee is separate from operational quality assurance activities in that its authority and responsibilities are not established by the Operational Quality Assurance Program. However, since the prime responsibility of this committee is to provide a continuing review of the operational and safety aspects of the station, it does perform a quality assurance function.

3. Manager - Nuclear Operations Support Responsible to the Vice President-Nuclear Operations to manage the system level support involving maintenance, operations, health physics, chemistry, procedures, and outage management services for the operating nuclear power stations.

a. Director - Health Physics/Chemistry

. Responsible to the Manager - Nuclear Operations Support for providing health physics and chemistry support services for nuclear*

stations. *

• 17.2-11

REVISION 23 12/94 SPS UFSAR

b. Director - Maintenance Support .

• Responsible to the Manager - Nuclear Operations Support for providing and assessing operations and maintenance programs, coordinating major' equipment repair or replacement, reviewing station efficiency, and for making recommendations for

• improvement.

c. Director- Methods and Procedures Responsible to the Manager - Nuclear Operations Support for the production and maintenance of corporate and station standards and administrative procedures and for coordinating station production and maintenance of station technical procedures.

C. Vice President - Nuciear Seryjces Responsible to the Senior Vice President - Nuclear and has corporate I

responsibility for long-term nuclear operations support activities. As such, he has responsibility for the system level implementation of the requirements established by the Operational Quality Assurance Program for the nuclear power stations.

1. Manager - Nuclear ucens;ng & Programs Responsible to the Vice President - Nuclear Services for providing overall direction, coordination and support of activities related to licensing, nuclear safety review and interactio.n with outside agencies to support safe, reliable and efficient operation of the power stations.

This includes serving as the lead interface with the Nuclear Regulatory Commission on regulatory issues, coordinating communications with outside organizations, such as INPO and NUMARC, and performing independent safety reviews of station activities and programs.

a. Director - Corporate Nuclear Safety Responsible to the Manager - Nuclear Licensing & Programs for providing overall direction for the Nuclear Group's independent safety review of station activities and programs. This includes nuclear safety assessments of company events, issues or trends, implementation of the industry operating experience program and performance of independent review of safety evaluations.

17.2-12

REVISION *23 12/94 SPS UFSAR a1 su~rvisQr - Nuclear Safely B~iew I

• Responsible to the Director - Corporate Nuclear Safety for providing independent performance based assessments of potentially significant nuclear safety events, issues, or adverse trends to identify underlying causes and recommend corrective actions. Supervise and support assessments to assure accomplishment of INPO performance objectives and regulatory requirements.

b. Supervisors - ucensing Responsible to the Manager - Nuclear Licensing and Programs for I

providing support for the stations in the areas of safety review, NRC issues and actions, and technical and strategic support for licensing and regulatory agency submittals, hearings, and conferences.

2. Director - Emergency Preparedness Responsible to the Vice President - Nuclear Services for managing the overall scheduling and coordination of emergency testing and training exercises* with federal, state, and local agencies. Works with corporate and nuclear station managers and personnel to ensure emergency plans meet all the requirements and. commitments.

3. Manager - Nuclear Training Responsible to the Vice President - Nuclear Services for training of personnel who operate or support the nuclear power stations, including Quality Assurance personnel. Training responsibilites include:

determining the need for training based on information provided by the Nuclear Group, developing performance-based training programs, implementing training programs to support employee and station needs, and evaluating training programs.

• 4. Manager - Nuclear Business Services Responsible to the Vice President - Nuclear Services for programs .

supporting budgeting, management reporting, document control, records management, publication design, and graphic support for the Nuclear Department. In addition, Nuclear Business Services is responsible for assessment of the programs' performance and follow-up actions to ensure program objectives are accomplished .

• 17.2-13

REVISION 23 12/94 SPS UFSAR

a. Director - _Nuclear Document Control . I Reports directly to the Manager - Nuclear Business Services and is

• responsible for development, implementation, maintenance and routine assessment of the Nuclear Document Management Program.

s. Manager - Nuclear Mateaals Responsible to the Vice President - Nuclear Services for ensuring that necessary parts and materials meeting quality and/or design requirements are available when needed.

The Superintendents - Materials and Director - Materials Management (Nuclear) report to the Manager - Nuclear Materials.

I D. Vi~e President - Nuclear Engineering Services I The Vice President - Nuclear Engineering Services is responsible to the Senior Vice President - Nuclear for civil, electrical, mechanical, and nuclear engineering, including establishment, implementation and maintenance of programs to control design input, final design, design output, internal and external design interface, and design authority. He is also responsible for procurement engineering, inservice inspection and

• nond e~tructive examrfination program~. nuclear fcored~esig_n_, saffety .

ana1ys1s, reactor pe ormance eva1uat1on, spent ue1 1spos1t1on, ue1 inspection, and fuel surveillance.

1. Manager - Nuclear Engineering Responsible to the Vice President - Nuclear Engineering Services for implementing the operational quality assurance program in the following areas:

• Implementation of engineering standards for nuclear design control.

• Engineering evaluation of generic industry issues.

• Management of engineering resources for specific tasks.

• Design Basis Documentation Program.

a. Supenntendent - Station Eng;neertng (one at each station) I Responsible to the Manager - Nuclear Engineering for the implementation of the operational quality assurance program in the following areas:

17.2-14

REVISION 23 12/94

• SPS UFSAR

• Implementation of the design change program at the site including initiating field changes as required .

Providing engineering disposition to Deviation Reports as required.

Managing the drawing update program.

• Managing engineering services as

• requested by station management.

2. Manager-Nuclear Analysis and Fuel Responsible to the Vice President-Nuclear Engineering Services forl the development and implementation of the operational quality assurance program in the following areas:

• Nuclear fuel management and core design

• Core and system thermal hydraulic analysis

• Fuel performance analysis

• Reload safety evaluation Engineering support for spent fuel disposition Post Accident Radiation Dose Calculation Reactor performance evaluation

• Special nuclear material accountability

• Inspection and surveillance of nuclear fuel and related items at the stations and vendors

" Engineering evaluation of fuel vendors

• Site reactor engineering

3. Manager ISi/NOE & Engineering Programs Responsible to the Vice President - Nuclear Engineering Services tori the lnservice Inspection (ISi) Program and the Nondestructive Examination (NOE) Services Program and other engineering programs in the following areas: * .

• 17.2-15

REVISION 23 12/94 SPS UFSAR

• Direction of the lnservice Inspection Program relative to sound judgment, company requirements, and regulatory and enforcement

• authority requirements.

• Management and assessment of the effectiveness of the lnservice Inspection Program through reviews, evaluations, and updates.

• Development of the inservice inspection programs, plans, and schedules.

• Development, maintenance, and implementation of the Nondestructive Examination Services Program.

• Performance and the technical aspects of nondestructive examinations.

• Qualification and certification of Virginia Power NDE personnel.

• Management and assessment of the effectiveness of procurement engineering.

• Control and implementation of General Engineering standards for nuclear design control.

• Engineering programs to maintain compliance with regulatory issues.

• Reviewing procurement documents.

• Managing the commercial grade procurement/dedication process .

Vendor manual control.

Managing the Equipment Data System (EDS) and Bill of Material System (BOM).

Managing the Q-list and equipment and component safety classification programs.

• Development and Maintenance of the Corporate Welding Manual.

• Provide material and metallurgical assessments and recommendations for existing and proposed new equipment.

• Provide material failure analysis and evaluations.

• Welding/corrosion engineering and fabrication support on in-house and AE/contractor designed material.

4. Managers - <CiviltMechanjcal and Etectncan Engineering Responsible to the Vice President - Nuclear Engineering Services.

• These managers provide engineering services through a project matrix organization to the Manager - Nuclear Engineering. Activities include.

preparation of design change packages and engineering evaluations, corporate administration of design engineering programs, control and implementation of discipline-specific engineering standards for nuclear 17.2-16

REVISION 23 12/94 SPS UFSAR design control, development of procurement specifications, construction drawings, technical reviews, calculations, etc.

E. Yice President - Procurement I The Vice President - Procurement is responsible to the Senior Vice President - Corporate Services for the acquisition of all fuels, materials,

• supplies, services, and transportation.

1. Manager - Contracts I Manager - Contracts is responsible to the Vice President-Procurement for performing contract administration functions in support of the

.operational quality assurance program for the nuclear power stations, except for fuel and fuel-related services.

I

2. Manager - Fuel Procurement I Manager - Fuel Procurement is responsible to the Vice President -

Procurement for the purchasing of nuclear fuel and related services, and to adhere to the provisions contained in the operational quality assurance program applicable to his_ respective area of responsibility.

I

3. Manager - Purchasing I Manager - Purchasing is responsible to the Vice President Procurement to procure the equipment, materials, supplies and general and technical services in support of the operational quality assurance program at the nuclear stations.

F. Manager-Nuclear OuaHty Assurance The Manager-Nuclear Quality Assurance is responsible to the Senior Vice I

President - Nuclear for the establishment of, and monitoring compliance with, the quality assurance program for engineering, construction, and operation activities of Nuclear Operations. The Manager - Nuclear Quality

. Assurance may make recommendations to the Vice President - Nuclear Operations, the Vice President - Nuclear Services, or other levels of management. If the Manager - Nuclear Quality Assurance disagrees with any action taken by the Nuclear group,* and is unable to obtain resolution, the Manager - Nuclear Quality Assurance shall bring the matter to the

• attention of the Senior Vice President - Nuclear who will determine the final disposition .

• 17.2-17

REVISION 23 12/94 SPS UFSAR

1. Manager-Quality Assurance {Station) {one at each site)

The Manager-Quality Assurance (Station) is responsible to t~e

• Manager - NuclearQuality Assurance for monitoring compliance with the operational quality assurance program for the nuclear power stations, conducting assessments of station activities and the technical support of the quality assurance effort associated with the modification, operation, and maintenance of the nuclear stations. The Manager -

Quality Assurance (Station) may make recommendations to the Station Manager or other levels of management. If he disagrees with any actions taken by the Station Manager, he shall notify the Manager -

I Nuclear Qu~lity Assurance and the Vice President - Nuclear Operations.

2. Manager - oualjty Assurance (Cor:porate) I The Manager - Quality Assurance (Corporate) is responsible to the Manager - Nuclear Quality Assurance for monitoring compliance with the quality assurance program, for conducting assessments of corporate and station activities, for scheduling and conducting internal audits, inspection and audit of vendors and contractors, preparation and maintenance of the Safety-Related Vendors List, quality review of safety-related procurement activities, and those areas of the operational quality assurance program as may be assigned to his area of responsibility. .

I

• G. Director - Nuclear Administrative Seryjces The Director - Nuclear Administrative Services is responsible to the Senior I

Vice President - Nuclear for Personnel/Human Resources, Management Information and Planning, and Fitness for Duty. Other responsibilities include: providing staff support to the Senior Vice President - Nuclear and coordinating international information exchange activities.

17.2.1.3 Organization I

Each nuclear power station's Technical Specifications contain company's organizational requirements for facility operation corporate management. Additionally, duties and responsibilities of positions within the nuclear organization are further defined in appropriate administrative controls.

the and key the I

17.2-18

REVISION 23 12/94 SPS UFSAR 17.2.2 OUALJIY ASSURANCE PROGRAM

• 17.2.2.1 General Description The objective of the Company Quality Assurance Program for operating nuclear power stations is to comply with the criteria as expressed in 10 CFR 50, Appendix 8, as amended, and with the quality assurance program. requirements for nuclear power plants as referenced in the Regulatory Guides and ANSI Standards as listed in table 17.2.0. This program, its policies and procedures are described herein: the Topical Report (VEP-1-5A) (entitled Operational Quality Assurance Program); the Quality Assurance Department Standards (QAOS); *the Nuclear Operations Department Standards (NODS); and the corporate and station procedures. This program applies to those quality-related activities that involve the functions of safety-related structures, systems, and components associated with the operation, maintenance and modification of nuclear power stations and those nonsafety-related components described in the UFSAR. Designated modifications may be performed under a contractor's Quality Assurance Program approved by the Company's Quality Assurance Program. The contractor's Quality Assurance Program when used for modifications will comply with the criteria expressed in 10 CFR 50, Appendix 8, as amended, and with the Regulatory Guides and ANSI Standards as listed in Table 17.2.0. .

The goal of this program is to assure the safe,* reliable and efficient operation of the nuclear power station in accordance with sound engineering principles.

• The program provides written policies, standards, procedures, and instructions

• covering engineering, design, procurement, modifications, periodic surveillance, testing, and maintenance after the systems have been installed, checked and turned over to the Company for operation. Nuclear Operations Department (NOD) policies and standards establish commitments to the Operational Quality Assurance Program.

Detailed procedures and instructions are issued by the station in accordance with and to meet the requirements of their Technical Specifications for administrative, normal operation, periodic testing, abnormal and emergency conditions. An audit and inspection program has been implemented to provide* assurance that these procedures are being correctly applied.

The Company quality assurance personnel, both station and corporate, report through a line of management completely separate from operational and production management and influences, and fulfill the following three-part role:

1. Audit assess and inspect to ensure that the overall operation of the nuclear power station is carried out in accordance with Technical Specifications,

_applicable codes and standards, NRC guides and regulations, company policies and commitments. ,

2. Serve as a management tool for station and system management personnel, illuminating problem areas, detecting trends, and providing recommendations regarding solution of problem areas when applicable .

• 17.2-19

REVISION 23

• 12/94 SPS UFSAR

3. Provide all levels of management with an independent source of information regarding the quality aspect of station operations, maintenance and

• modification activities.

• Differences of opinion between quality assurance personnel and other departments

' are resolved either at the manager level by the cognizant Manager and the Manager -

Quality Assurance or are forwarded through normal administrative chains of both individuals for resolution at the corporate level. Final decision-making authority rests with the Senior Vice President-Nuclear.

The Quality Assurance Department conducts audits and inspections in accordance with the Operational Quality Assurance Program and performs other duties as directed by the individual Supervisors-Quality. The Quality Assurance Department representatives have access to all areas of the station at any time deemed necessary for inspections, audits, and observations related to quality. They have access to station records required for in-depth auditing of station operations, including confidential personnel records (but only to the extent necessary to verify personnel qualifications or other information related to quality.)

• 17.2.2.2 Quality Assurance Program The Company Operational Quality Assurance Program is displayed in a point-by-point comparison to Appendix B, 10 CFR 50 in Table 17.2.2, which follows. * *

• 17.2-20

REVISION 23 12/94 . SPS UFSAR 17.2.2.3 Identification of Structures, Systems, and Components

• Safety related structures, systems, and components are identified in the UFSAR. The portions of these structures, systems, and components that are within the scope of the Operational Quality Assurance Program are further identified in the respective Q-List for North Anna and Surry Power Station.

17.2.2.4 Periodic Review of the Operational Quality Assurance Program Audits of activities required by the Operational Quality Assurance Program will be conducted at least once per 24 months. These audits are performed under the cognizance of the Management Safety Review Committee.

17.2.2.5 Qualification of Quality Assurance Department Personnel The Manager - Quality Assurance (Corporate) shall have a four-year accredited engineering or science degree or equivalent with a minimum of ten years experience related to electric po"wer generating facilities. At least five years of overall experience shall have been in a supervisory capacity, two years of which should have involved quality assurance related matters.

The Manager - Quality Assurance (Station) shall have a four-year accredited engineering or science degree or equivalent with a minimum of eight years experience related to electric power generation facilities, two years of which involve experience in nuclear power stations. At least four years of overall experience shall have been in a supervisory capacity, two years of which should have involved quality

• assurance related matters .

The Supervisors - Quality shall have a four-year accredited engineering or science degree, or equivalent. A minimum of two years overall experience or equivalent training in power plant operations is a prerequisite with at least one year of this experience involved in nuclear power station quality assurance program implementation.

Replacement personnel in the key positions listed will meet or exceed the applicable requirements of ANSI/ANS 3.1 (Draft 12/79) as clarified in Table 17.2.0.

• 17.2-21

REVISION 23 12/94 SPS UFSAR 17.2.2.6 Certification of Quality Assurance Department Personnel The certification of Quality Assurance Department personnel is accomplished in accordance with the Quality Assurance Certification Program. This program provides for the certification and recertification of Level I, Level II and Level Ill inspectors, and for auditors and lead auditors.

The program outlines the qualification and certification requirements for personnel and requires the individual to be certified prior to performing specified inspection or audit functions. The Supervisor - Quality has the responsibility to certify/qualify inspection/audit personnel.

17.2.2.7 Certification of Other Support Personnel

. The certification of Quality Maintenance Team (QMT) personnel, Material Verification personnel, Fuel Accountability and Inspection personnel, and lnservice Testing personnel i~ accomplished in accordance with the approved certification programs.

These programs outline the qualification and certification requirements of personnel and require the individual to be certified prior to performing specified functions. The Supervisor - Quality has the responsibility to certify/qualify Quality Maintenance Team (QMT) personnel.

17.2-22

REVISION 23

• 12/94 SPS UFSAR 17.2.3 DESIGN CONTROL

• Nuclear Standards describe the design control program. Measures are established to assure that applicable regulatory requirements and the nuclear power station design bases are correctly translated into the Company specifications, drawings, procedures, and instructions applicable to design changes and/or modifications for the operating nuclear power station.

All design changes and/or modifications to safety-related structures, equipment, systems and components described in the UFSAR are reviewed, approved, and acted upon by the Station Nuclear Safety and Operating .Committee in accordance with their responsibilities and functions as referenced in the Technical Specifications. The Management Safety Review co*mmittee is responsible for ensuring that independent reviews are performed for safety evaluations associated with design changes approved by the Station Nuclear Safety and Operating Committee. The responsibility for the development, identification of requirements, monitoring, and implementation of an effective design control program is delegated to the Vice President - Nuclear Engineering Services with input as appropriate. from the Station Manager and operations personnel.

The Nuclear Design Control Program (NDCP), delineates procedures that assure design changes, including field changes, are subject to* design control measures commensurate with those applied to the original design and the applicable specified design requirements. These procedures assure that design basis, regulatory requirements, codes and standards are correctly translated into specifications, drawings, procedures, or instructions for those structures, systems and components

• classified as safety-related in the UFSAR and Q-List. The NDCP provides for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program. When a testing program is solely used to test the adequacy of a design, the test will be conducted under adverse design conditions. The provisions of this section assure that the verifying or checking process is performed by individuals other than those who performed the original design. These individuals are identified and their authority and responsibility is described. The NDCP also identifies the design documents that are required to be reviewed and the personnel responsible for their review and revisions, to assure that design characteristics can be controlled, inspected and tested, and that inspection and test criteria are identified. Design change documents and revisions thereto are distributed to responsible supervisors to determine whether revisions to controlled design and operating documents are necessary. Design documents and reviews, records and changes thereto are collected, stored and maintained in a systematic and controlled manner.

The NDCP establishes measures for the selection and review for suitability of application of materials, parts, equipment and processes that are essential to the safety-related functions of the systems, structures and components. These measures include the use of valid and applicable industry standards and specifications.materials and prototype hardware testing programs, and design reviews. In the event of a design modification to a system which is safety related, engineering studies

• 17.2-23

REVISION 23 12/94 SPS UFSAR are initiated to evaluate parts, equipment, processes, and material suitability for repair

• of such equipment or components; previously approved items are used without further review. Previously approved materials, parts or components used for a different application are reviewed for suitability prior to approval for their new application.

Quality measures are assured through all levels of the design control program by the design control organization, the Design Control Engineer, Engineering Supervisors, Superintendent - Station Engineering, Manager - Nuclear Licensing and Programs, and the Station Nuclear Safety and Operating Committee. Any errors or deficiencies noted in the design process are documented on the design change forms and subsequently corrected.

Procedures for design controls, analysis, and reviews have as their basis the applicable portions of documents referenced in the Nuclear Design Control Manual, and include ANSI N45.2.11 - 1974 as modified in Table 17.2.0.

The Nuclear Design Control Program Instruction Manual for ArchitecVEngineers establishes procedures to describe the design interface between the Company and contractors for the review, approval, release, distribution, and revision of documents involving design interfaces.

Suitable design controls are applied to such disciplines as reactor physics; seismic stress, thermal, hydraulic, radiation and accident analysis, compatibility of materials; and accessibility for inservice inspection, maintenance and repair. Designs are reviewed to assure that (1) design characteristics can be controlled, inspected,

• and tested, and (2) inspection and test criteria are identified.

Changes to nonsafety-related structures, systems, and components will be controlled in accordance with applicable procedures and to meet the requirements, where applicable, of 10 CFR 50.59.

The Quality Assurance Department reviews the implem*entation of the design control measures through inspections and audits.

17.2-24

REVISION 23 . 12/94 SPS UFSAR 17.2.4 PROCUREMENT DOCUMENT CONTROL

• Nuclear Operations Department Standards and their supporting procedures describe the program for completing procurement documents including review, approval, document control, and change control. In addition, references to procedures that govern the actions of the Quality Assurance (Corporate) are made which include provisions for access to the suppliers facilities and records, for source inspection and audit by quality assurance personnel, and qualification of vendors prior to the initiation of quality related actions when the need for such inspection and/or audit has been determined. This program also provides for records to be prepared, maintained, made available for review, or delivered to the Company prior to use or installation of the hardware, such as drawings, specifications, procedures, procurement documents, inspection and test records, personnel and procedure qualifications, material, chemical and physical tests results, an the identification of quality assurance requirements applicable to the items or services purchased, including sub-tier procurement requirements when required.

Policies and standards are established in the Nuclear Department Standards Manual to ensure that procurement documents reference all actions required by a supplier in accordance with the applicable codes, specifications, and drawings.

Procurement documents incorporate the design basis technical _and quality requirements including the applicable regulatory requirements, component and material identification requirements, drawings, specifications, codes and industrial standards, test and inspection requirements, and special instructions for special procedures such as welding, heating treating, nondestructive testing and cleaning as applicable .

Procurement documents for spare or replacement parts of safety-related structures, systems and components are subject to technical and quality controls at least equivalent to those used on the original equipment.

The procurement document, a copy of which is filed and available for review, is prepared by the cognizant supervisor and then undergoes the review and approval routing as determined by the Procurement and Materials Management Process Manual. These reviews and approvals are documented.

The Quality Assurance Department periodically *audits the control of procurement documents.

• 17.2-25

REVISION 23 12/94 SPS UFSAR 17.2.5 INSTRUCTIONS, PROCEDURES, AND DRAWINGS As required by the individual unit's Technical Specifications, detailed written procedures are established, approved, implemented, and maintained.

Other activities affecting quality of structures, systems, and components within the scope of 10 CFR 50 Appendix B are prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances. These activities are accomplished in accordance w_ith these instructions, procedures, or drawings.

Applicable instructions, procedures, or drawings include for reference appropriate qualitative and/or quantitative acceptance criteria for determining that important activities have been satisfactorily accomplished.

Administrative procedures describe the requirements for developing, reviewing, approving, and controlling procedures used for testing as well as corrective maintenance, operating, design change implementation, administrative, and other activities performed at the power station.

• These requirements include references, prerequisities, precautions, limitations, manufacturer's specifications, check-off lists, and acceptance criteria (as appropriate). When applicable the acceptance limits and requirements contained in the design and procurement documents constitute a portion of the acceptance criteria referenced and contained in written testing procedures.

The Quality Assurance Department periodically reviews the documents to ensure revisions are made promptly and that obsolete material is deleted. They have the authority to recommend changes and to require the addition/deletion of inspection hold/verification points. Through their stop work authority they can prohibit the use of inappropriate documents until correct documents can be obtained.

17.2-26

REVISION 23 12/94 SPS UFSAA

• • 17.2.6 DOCUMENT CONTROL Measures are established and documented within the operating nuclear power stations and at Innsbrook Technical Center describing the control of documents, such as procedures, instructions, and drawings, to provide for their review, approval, and issue, and changes thereto, prior to release and to assure they are adequate and the quality requirements are stated. Provisions call for, among other things, (1) the review and approval of all new station procedures and design changes prior to release, the review and approval of all changes/revisions to station procedures and all proposed changes or modifications to plant systems or equipment that affect nuclear safety by I

the Station Nuclear Safety and Operating Committee, {2) policy and procedures for issuance of and .changes to station drawings and approval of changes, and (3) the maintenance and distribution of these procedures. Normally change$ to documents are reviewed and approved by the same organizations that performed the original review and approval; however, this responsibility may be delegated to other qualified responsible organizations. Approved changes are incorporated into procedures and drawings and other appropriate documents associated with the change. Procedures and drawings and changes thereto are processed, distributed and controlled. The station maintains a record of all holders of procedures and drawings and an index of all procedures and drawings, listing the current revision date. Instructions require that a copy of the appropriate procedure be available at the activity location prior to the commencement of that activity. These measures are addressed in the Technical Specifications and Administrative Procedures for each station.

Administrative procedures list certain documents that require strict administrative control for distribution, revision, and routing. These documents are

• categorized as "Controlled Documents." Examples of controlled documents are:

Station Procedures, Station Drawings, and the Precautions, Limitations, and Setpoint Document. Also set forth are the distribution and controlling procedures for design and procurement documents. The Quality Assurance Department makes periodic inspections and audits of documents to verify their status, using a current master copy .

• 17.2-27

REVISION 23 12/94 . SPS UFSAR 17.2. 7 CONTROL OF PURCHASED MATERJAL, EOUJPMENT, AND SERVICES An evaluation of suppliers is performed prior to contract award, except in emergency situations where an item or service is needed to preclude development or deterioration of an unsafe condition at the plant, by one or more of the following: (1) A review of the supplier's capability to comply with the elements of 10 CFR 50, Appendix B that are applicable to the type of material, equipment, or service being procured, (2)

A review or previous records and performances of suppliers who have provided similar articles of the type being procured, (3) A survey of the supplier's facilities and quality assurance program to determine his capability to supply a product or service which meets the design, manufacturing, and quality requirements, or (4) A review of qualification information supplied by another utility or outside organization.

Surveillance of suppliers during fabrication, inspection, testing, and st)ipment of materials, equipment, and components is planned and performed in accordance with written procedures to assure conformance to the purchase order requirements as applicable. These procedures provide for:

a. Instructions that specify the characteristics or processes to be witnessed, inspected or verified, and accepted; the method of surveillance and the extent of documentation required; and those responsible for implementing these instructions. Surveillance shall be performed on those items where verification of procurement requirements cannot be determined on receipt.

b. Audits and/or inspections which assure that the supplier complies with all quality requirements.

These evaluations are performed under the supervision of the Manager -

• Quality Assurance (Corporate), except for surveillance of nuclear fuel related suppliers. The surveillance of suppliers of nuclear fuel and related items is performed under the supervision of the Manager - Nuclear Analysis and Fuel. The results of these actions are documented and filed.

Administrative procedures describe the requirements for controlling purchased material, equipment, and services including commercial grade items for use on safety-related structures, systems, equipment, and components. The requirements applied to spare and replacement parts are at least equivalent to those applied to the original parts. Periodic inspections by the Materials Management Department are made for assuring that applicable material and equipment received at the station meet the

• requirements of the specifications, purchase orders, code, drawings, or other purchasing documents. This assurance includes the review of documentation received, physical inspection, cleanliness, packaging, marking or functional testing, 2.s required. Purchased items are normally under the control of the "on-site" organization.

This organization is authorized to contact system organizations and NSSS, A/E contractors and subcontractors through the auspices of system representatives for assistance as . required. Monitoring and verification of .these activities are performed under the supervision of the Manager-Quality Assurance (Corporate).

I Periodic evaluations or monitoring of procurement history of the suppliers are performed to verify continued supplier capability.

17.2-28

REVISION 23 12/94 SPS UFSAR Documentation concerning the quality of material, components, and equipment

• received is reviewed by the Materials Management representative for conformance with the Purchase Requisition and Purchase Order.

The procurement of nuclear fuel* is controlled in accordance with procedures that have been developed by the Engineering and Procurement Organizations to address the requisite quality attributes of this function. Monitoring and verification of I

this activity is performed under the supervision of the Manager - Quality Assurance (Corporate) .

• 17.2-29

REVISION 23 12/94 SPS UFSAR

. 17.2.8 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS, AND COMPONENTS Installed components at the nuclear power station are adequately identified and .

• substantiated with documented records by the Architect - Engineer and the NSSS Vendor during the construction phase of the station. These identifications and records are maintained in the station files.

Replacement materials, parts, and components including partially fabricated subassemblies ~re adequately and properly identified to allow control and traceability to pertinent quality assurance records such as drawings, specifications, purchase orders, manufacturing and inspection documents, deviation reports, and physical and chemical mill test reports. The identification system is consistent, as practical, with that used during the construction of the station, with similar identification used during design change activities. The location and method of identification do not affect the function or quality of the item being identified. Verification of correct identification of safety-related materials, parts, and components is required and documented prior to the release for fabrication, assembling, shipping, or installation.

The Quality Assurance Department periodically performs inspections and audits of this activity.

17.2-30

REVISION 23 12/94 SPS UFSAR 17.2.9 CONTROL Of SPECIAL PROCESSES

• The control of special processes is maintained and implemented through the use of procedures, technique sheets, travelers and inspection verification reports, and personnel qualified in accordance with the applicable codes, specifications, and standards for the specific work. In instances where the Company assigns such work to contractors, the contractor must submit their procedures and personnel qualifications to the Company for approval prior to the start of work.

Special processes include, for example, those involving welding, heat treating, nondestructive testing, cadwelding, removal of undesirable substances during shop and site cleaning, degreasing and flushing, and verification of wall thickness of valves and other cast components important to nuclear safety.

The Company conducts inspections of work involving special processes to assure that procedures and personnel are properly qualified and their workmanship is in compliance with ~pplicable specifications, codes, and standards.

Records of procedures, equipment, and personnel qualification are maintained and kept current _in accordance with the provisions of Section 17.2.17 herein.

Monitoring and verification is performed by the Quality Assurance Department.

• 17.2-31

REVISION 23

• 12194 SPS UFSAR 17.2.1 o INSPECTION Inspection procedures for those activities affecting quality have been established. These procedures govern the inspection and documentation of activities relating to repairs, modifications, and changes made to safety related systems, structures, and components. Written maintenance procedures are provided which include inspection hold points.

Examinations, measurements, or tests of materials or components associated with safety-related equipment and systems are performed for each work operation, where necessary, to assure quafity. If inspection is impossible or inappropriate, indirect control by monitoring methods, equipment, and personnel is provided. Both methods are provided when control is inadequate without both.

The station safety-related maintenance procedures (including modification procedures) are reviewed by the Supervisor-Quality or designee (Inspections) to determine the need for an independent inspection and the degree and method if such an inspection is required. Examinations, measurements, or tests that require witnessing are identified as "inspection hold" points in procedures. The inspection performed at a hold point is specific in nature; quality characteristics and acceptance/rejection criteria are included or qualitative criteria such as operability checks, compliance with procedural steps, or cleanliness instructions ar~ specifieq.

The inspection is documented by signature or initials on the written procedure form.

Quality Assurance Department performs physical inspections at random intervals to ensure quality requirements are met. These checks are performed as the conditions of the maintenance warrant. These personnel and other inspectors are

• qualified in accordance with codes and standards as applicable to the function they are performing.

The inspection program requires that inspectors be assigned as appropriate for the activity being inspected. An inspector may be a member of the organization performing the activity. However, they must be.qualified and shall not be the person performing the activity or the supervisor directly responsible for the activity. For example, Quality Maintenance Team personnel when performing Quality Control inspections are under the direction of the Supervisor - Quality (Inspection). Personnel so assigned shall become familiar with the procedure being used and other pertinent documents such as technical manuals and drawings prior to performing the inspection.

Personnel responsible solely for the conduct of nondestructive examination ars qualified to SNT-TC-1A as referenced by Table IWA-1600-1 of the applicable Code. In addition, personnel who conduct inservice or preservice examinations meet the additional and/or alternative qualification requirements specified by IWA-2300 for the applicable examination method and qualification level. Audits and reviews of their findings and associated corrective actions are periodically conducted by quality assurance personnel to assure that these procedures are being carried out in a quality manner. The inspectors qualifications are periodically reviewed for recertification .

17.2-32

REVISION 23 12/94 SPS UFSAR Generally, all physical inspections are under the control of the on-site

• organization. However, the Station Manager is authorized to request assistance as required through the Manager - Nuclear Operations Support as does the Supervisor -

Quality via the Manager - Quality Assurance (Station).

The inspection of nuclear fuel and related items is controlled in accordance with procedures that have been developed by Nuclear Analysis and Fuel to address the requisite quality attributes of this function. Monitoring and verification of this activity is performed under the direction of the Manager - Quality Assurance (Corporate).

Additionally, inspection activities pertaining to Design Control (Section 17.2.3);

Procurement Document Control (Section 17.2.4); Test Control (Section 17.2.11 );

Nonconforming Materials, Parts, or Components (Section 17.2.15); and. Corrective Action (Section 17.2.16) shall be controlled in accordance with provisions established for this function in the referenced sections contained herein .

• 17.2-33

REVISION 23 12/94 SPS UFSAR 11.2.11 TEST CONTROL The test program described in the Technical Specifications assures that safety-related structures, systems, and components will perform satisfactorily when required.

Written "Periodic Test" procedures for this program are reviewed and approved as specified in the individual unit's Technical Specifications. These test procedures include or reference:

(1) The requirements and acceptance limits contained in applicable design and procurement documents.

(2) Test prerequisites such as the availability of adequate and appropriate equipment and calibrated instrumentation; trained, qualified, and licensed or certified personnel; the completeness of the item to be tested; suitable and controlled environmental conditions; provisions for data collection and storage.

(3) Instructions for performing the test.

(4) Inspection points as appropriate.

(5) Acceptance and rejection criteria.

(6) Methods of documenting or recording test data and results.

The Periodic Test Program provides for testing of instrumentation and electrical equipment in the categories of (1) instruments installed as listed in the Technical

• Specifications, (2) installed instrumentation used to verify Technical Specification parameters, and (3) installed safety-related instruments and electrical equipment that provide an active function during operation, shutdown, or abnormal conditions (i.e.,

vice being designated safety-related solely because the instrument is an integral part of a pressure retaining boundary). This instrumentation shall be in a calibration program. This program provides, by the use of equipment history data, status, records, and performance schedules, for the date that calibration is due and indicates the status of calibration. The identity of person(s) performing calibration is provided on the calibration documents.

Testing of modifications is done in accordance with procedures developed within the Design Change Program described in Section 17.2.3 of this report.

Testing upon completion of maintenance is done in accordance *with Maintenance Procedures developed as described in Section 17.2.5 of this report.

Monitoring and verification is performed by the Quality Assurance Department.

17.2-34

REVISION 23

• 12/94 SPS UFSAR 17.2.12 CONTROL OF MEASURING AND TEST EOUJPMENT

• A program has been established and documented in administrative procedures that describes the calibration technique and frequency, maintenance, and control of all "Measuring and Test Equipment" (portable instruments, tools, gauges, fixtures, reference and transfer standards, and nondestructive test equipment) which are used in the measurement, inspection, maintenance, and monitoring of safety-related components, systems, and structures. Measuring and test equipment does not include: measuring equipment used for preliminary checks or utility troubleshooting where accuracy is not required. There is also no intention to imply a need for special calibration and control measures of rulers, tape measures, levels, and other basic tools if normal commercial practices provide adequate accuracy. Controls for measuring and test equipment include the transportation, storage, and protection of the equipment; the handling of associated documents giving the status of all items under the calibration system such as maintenance history, calibration test data, and individual log sheets assigned to each device; and the permanent marking of each device .by a unique ~umber.

The maintenance, calibration technique, and frequency of calibration of measuring and test equipment utilized in activities affecting quality at the power station are normally performed as specified in the manufacturer's instruction manual or in approved written procedures. In some cases the calibration interval may be assigned or changed based on accumulated experience by trained technicians. The recall system may include provisions for the temporary extension of the calibration due date under certain conditions specified in approved procedures. If standards are not available or there is some special reason that procedures cannot be followed, the

• modified procedures and/or interval are documented, including justification. In other cases, rather than require calibration at specified intervals, procedures may specify the device be calibrated prior to use, as in the case of torque wrenches or mircometers.

Where permitted by commercially available state of the art equipment, reference standards are no more than 1/4 the error allowed in the measuring and test equipment calibrated by that standard. Measuring and test equipment used on safety-related

.~1 systems or equipment are calibrated utilizing reference standards whose calibration *.,1 has a known valid relationship to nationally recognized standards, such as the National Institute of Standards and Technology (NIST), or accepted values of natural physical constants. If no national standard exists, the basis for calibration is documented. Whether the device is calibrated at the power station or at an NIST traceable outside laboratory, one or more stickers are affixed on a conspicuous surface identifying, but not limited to, date of calibration and next calibration due date.

When measuring and test equipment utilized in activities affecting quality are found to be out of calibration an evaluation will be performed and documented ..

concerning the validity of previous tests and the acceptability of devices previously tested. All previous tests and measurements performed during the current or proceeding calibration cycle shall be redone if the evaluation so indicates.

Implementation of these procedures is assured through routine inspections or audits by the station Quality Assurance Department.

• 17.2-35

REVISION 23 12/94 SPS UFSAR 17.2.13 HANPUNG, STORAGE, ANO SHIPPING Measures have been established in administrative procedures to provide adequate. methods by qualified personnel for the classification, packaging, cleaning, preservation, shipping, storage, and handling of material and equipment received at the station.

These measures, prepared in accordance with .design and specification requirements, define responsibility, levels of essentiality, degree of receipt inspection, tagging, categories of inspection and their definition, and storage levels for categorized items. The procedures also control cleaning, handling, storage, packaging, shipping, and preservation of materials, components, and systems to preclude damage, loss, or deterioration by environmental conditions such as temperature or humidity. Implementation of these measures is verified by audits and inspections.

• 17.2-36

REVISION 23* 12/94 SPS UFSAR 17.2.14 INSPECTION, TEST, AND OPERATING STATUS

• Measures for the identification and documentation of the inspection and test status for items to prevent inadvertent bypassing of specified inspections and tests are established in administrative procedures and in station operating procedures. These measures define the three general categories of inspection and test status for items:

Accept, Reject, or Hold. They provide for status identification through the use of stickers, tags, record cards, test records, check-off lists, or logs. The operating status of items and/or equipment is identified through records, checklists, or operational tagging systems that are maintained to indicate the status and authority to operate the item and/or equipment. Operating status is additionally controlled through the normal station operating procedures. The application and removal of the various status tags,

• stickers, and other indicators is controlled by Station Procedures. Implementation of these measures is verified through audits and inspections conducted in accordance with the Operational Quality Assurance Program. These activities assure that the required inspections, tests, and other critical operations are controlled .

• 17.2-37

REVISION 23 12/94 SPS UFSAR 17.2.15 NONCONFORMING MATERIALS, PARTS, AND COMPONENTS A documented system for controlling nonconformances observed during receipt inspection, storage, fabrication and erection, installation, initial and/or acceptance testing, or initial operation is established and provides for the preparation, issuing, and distribution of Station Deviation Reports and Discrepant Shipment Reports in I accordance with prescribed procedures. These procedures apply to new or reworked materials, parts, or components which possess manufacturer/supplier caused nonconformances.

The identification, documentation, segregation,

• review, disposition, and notification to affected organizations of nonconforming material, parts, or components are described or referenced in station Technical Specifications, Administrative procedures, and/or station operating procedures. Nonconformance of purchased services are controlled under Section 17.2.7 Control of Purchased Material, Equipment, and Services; Section 17.2.10 Inspection; and administrative procedures.

Specifically,* instructions require that the individual discovering a nonconformance identifies, describes, and documents the nonconformance on a Station Deviation Report or a Discrepant Shipment Report in accordance with administrative procedures.

I When a nonconforming item is identified, it is placed in the hold area established in the storeroom or other segregated location, if practical, and identified with a hold tag to prevent its inadvertent use. If material is dispositioned as 'reject' the hold tag shall remain attached to the material/component until loaded for departure from site and shall only be removed in accordance with approved procedures by authorized personnel at that time.

I*

Hold items may be released on a risk basis following the documented approval of such risk release by the Station Manager on a Release on a Risk Basis Form. Each risk release is handled on a case basis and depends on the nature of the hold status.

The basis and conditions of the *release are described on the form, including the criteria for clearing the original hold status. Rejected material is not risk released.

A Station Deviation Report or a Discrepant Shipment Report for a nonconforming material, part, or component dispositioned "accept as is" requires an engineering analysis and approval. The results of this review and approval are documented and become a part of station records.

Should the disposition of a nonconformance require the rework or repair of materials, parts, components, systems, or structures, such rework or repair is reinspected or retested by a method which is at least equal to the original inspection or test method. The inspection requirements and the inspection, rework, or repair procedures are documented and become a part of station records.

• 17.2-38

REVISION 23 12/94 SPS UFSAR The disposition and approval of nonconformances are the responsibility of the

• on-site organization. However, the Station Manager has the authority to request assistance as appropriate from off-site organizations such as Nuclear Operations Support, other engineering groups, or the Quality Assurance Department.

The Station Deviation Reports trends are periodically reviewed for conditions adverse to quality by station management.

In service failures of materials, parts, and components are dispositioned by the use of Deviation Reports and/or Work Orders as described in Section 17.2.16 of this report.

Implementation and verification of the procedures for the control of nonconformances are assured through audits and inspections by the Quality Assurance Department.

The nonconformances observed during the inspection of nuclear fuel and related items and* the disposition of those nonconformances is controlled in accordance with procedures that have been developed by Nuclear Analysis and Fuel to address the requisite quality attributes of this function. Monitoring and verification of this activity is performed under the direction of the Manager - Quality Assurance (Corporate) .

• 17.2-39

REVISION 23 12/94 SPS UFSAR 17.2.16 CORRECTIVE ACTION Corrective action measures are established as an integral part of the processing and resolving of nonconformances and failures in service. Through these measures, assurance is confirmed that significant adverse quality conditions are identified, documented, their cause determined, and the corrective actions have bee*n taken that preclude repetition of the adverse quality conditions. Verification of the proper implementation of corrective action measures and closeout of corrective action documentation is assured through the monitoring effort of the station staff and the follow-up reviews and audits conducted by the Quality Assurance Department.

Adverse conditions significant to quality, the cause of the conditions, and the initiation of corrective action are reported to appropriate levels of both offsite and onsite management by use of Deviation Reports and audit findings. If further corrective action is required the appropriate management program for performing, tracking and closing the issue will be used.

Nuclear Engin_eering Services maintains a program to evaluate complex design concerns that may lead to adverse quality conditions at the Nuclear stations. The Potential Problem Reporting (PPR) system allows for detailed, multidiscipline reviews of complex design concerns that may yield station deviation reports. Many design concerns cannot be determined to be adverse to quality until a detailed design review is performed. The PPR process controls this activity as part of the Nuclear Design Control Program.

The procedures for processing a Deviation Report require that each adverse condition significant to quality be categorized as either requiring a Licensee Event

• Report, Special Report or NRC Notification or as a nonreportable deviation.

Nonreportable deviation refers to deviations not reportable to the Nuclear Regulatory Commission. The reporting requirements differ for each of the categories of deviation but require the appropriate levels of management be notified in each case. The Quality Assurance Department periodically audits the deviation reporting process.

Procedures require that corrective maintenance of nuclear safety related material, parts, or components be documented on a Work Order. The Quality Assurance Department is notified prior to the commencement of safety related maintenance. The Quality Assurance Department may then initiate a surveillance program as necessary. Examples of areas subject to surveillance are (1) the use of approved maintenance procedures, (2) the existence of Radiation Work Permits and proper tagout, if applicable, (3) the existence of required plant conditions, and (4) documentation of Technical Specification requirements. If the Quality Assurance Department elects to inspect the work, the surveillance does not have to be performsd prior to commencement of work. Also, the Quality Assurance Department monitors completed Work Orders to assure maintenance performed is properly documented, maintenance procedures are properly signed off and check lists are completed if applicable, Technical Specification limits were met if applicable, materials used are documented, and Work Orders are being adequately reviewed by appropriate supervisory personnel.

17.2-40

REVISION 23 12/94 SPS UFSAR

• • Station Technical Specifications require that rework or repai.r of nuclear safety-related materials, parts, components, systems, and structures be accomplished in accordance with approved written procedures. The procedures for rework or repair of safety-related equipment are approved by the Station Nuclear Safety and Operating Committee to ensure provisions for an adequate inspection of the completed rework or repair and that this inspection is a method at least equal to the method originally used for inspection or an acceptable alternative. The cognizant supervisor reviews the completed procedures to insure the acceptance criteria have been satisfied and for the completeness of the post-maintenance check-out. The station Quality Assurance Department monitors completed procedures to assure adequate supervisory review.

The Supervisor - Quality determines the scope of the required quality assurance effort on the basis of the extent of modifications or repair to safety-related equipment, systems, or components. When this determination is made, the station Quality Assurance Department reviews the proposed procedures to be used for the modification or repair activities to ensure hold points are included, the procedure complies with the operational quality assurance program, and the applicable codes .

and standards are referenced. For some repair efforts, briefings of quality assurance personnel by the Supervisor - Quality are conducted. For major evolutions, such as refueling, steam generator modifications, etc., a series of seminars covering all aspects of the activity (e.g., radiation control, personnel hazards, stop work procedures, inspection criteria) may be held.

17.2.16.1 Authority to Stop Work The Quality Assurance Department has the authority, and the responsibility, to stop work in progress which is not being done in accordance with approved procedures or where safety or equipment integrity may be jeopardized. This extends to off-site work performed by vendors furnishing safety-related materials and services to the Company.

17.2.16.2 Imposition of "Stop Work" A. Station Quality Control Staff - The station Quality Assurance Department representative advises the cognizant supervisor or supervisory personnel to stop work in progress whenever he determines that it is not being conducted in accordance with applicable procedures, instructions, guides, or standards or may jeopardize the safe operation of the station. The Supervisor-Quality immediately notifies the Station Manager of the decision to stop work because of adverse quality conditions. He shall also notify the Manager-Quality Assurance (Station).

B. Station Manager - The Station Manager evaluates the Quality Assurance Department's determination of the necessity to stop work.

1. If he concurs with the decision to stop work, he initiates the necessary corrective action. Only after the discrepancy has been corrected and the corrective action approved by the Quality Assurance Department

• does work resume .

• 17.2-41

REVISION 23

• 12/94 SPS UFSAR

2. In the event the Station Manager does not concur with the Quality Assurance Department's decision to stop work, he may order work to

• resume by

• notifying the Manager-Quality Assurance and the appropriate station supervisory personnel in his organization of his decision. He shall also refer the issue to the Vice President-Nudear Operations for review and approval.

C. Vjce Presjdent-Nucjear Operatjons - The Vice President-Nuclear Operations is responsible for approving or disapproving the Station Manager's decision in those cases where the Station Manager does not concur with the stop work and orders work to resume.

D. Manager-Quality Assurance - The Manager-Quality Assurance (Station) may refer any concerns he may have concerning the handling of "stop work" to the Vice President-Nuclear Operations or to the Manager-Nuclear Quality Assurance.

He may direct imposition of "stop work" whenever he deems such action to be appropriate.

E. Imposition of offsite "stop work" performed by vendors shall be controlled by appropriate administrative procedures.

17.2-42

REVISION 23 12/94 SPS UFSAR 17.2.17 OUAUTY ASSURANCE RECORDS The requirements and responsibilities for quality assurance records transmittal, retention, and* maintenance subsequent to completion of work at the power station have been established and are documented in administrative procedures .

Quality Assurance records relating to the operating status of the station and documentary evidence of the quality of items and activities affecting quality are maintained in accordance with the Technical Specifications and administrative procedures. These records include plant history; operating logs; principal maintenance and modification activities; Licensee Event Reports; results of reviews, inspections, tests, audits, and material analysis; monitoring of work performance, qualification of personnel, procedures, and equipment; and other documentation such as drawings, specifications, procurement documents, calibration procedures and reports, deviation reports, and corrective action requests.

Identification and retrievability of these records is facilitated through proper indices and an established basic filing system. Record storage facilities are constructed, located, and secured to prevent the destruction of records by fire, flooding, theft, .and deterioration through environmental conditions such as temperature and humidity.

The Quality Assurance Department monitors these records to assure their completeness, adequacy, retrievability, and protection. They periodically audit these records to verify implementation of established policies and procedures. The record

• storage facilities conform to Regulatory Guide 1.88, Rev. 2 October 1976, as stated in Table 17.2.0 .

• 17.2-43

REVISION 23 . 12/94 SPS UFSAR 17.2.18 AUDITS The system of audits devised to verify compliance with quality related aspects of the power station is described in the station Technical Specifications. Audits of selected aspects of operational phase activities are performed with a frequency commensurate with safety significance and in a manner which assures that biennial (2 years) audits of safety related activities are completed. The audits are regularly scheduled on a formal preplanned audit schedule. The audit system is reviewed periodically and revised as necessary to assure coverage commensurate with current and planned activities. Additional audits may be performed as deemed necessary by management. The scope of the audit is determined by the quality status and safety importance of the activities being performed. These audits are conducted by trained personnel not having direct responsibilities in the area being audited and in accordance with preplanned and approved audit plans or checklists.

The Quality Assurance Department is delegated the responsibility for conducting periodic audits to determine the adequacy of the station's programs and .

procedures, that the*y are meaningful, and comply with the overall Quality Assurance Program. An audit includes an objective evaluation of quality related practices, procedures, and instructions; the effectiveness of implementation; and the conformance with policy and directives. An audit also includes the evaluation of work area, activities, processes, and items and the review of documents and records.

Provisions are established requiring that audits be performed in those areas where the requirements of Appendix B to 10 CFR 50 are being implemented. These* areas include as a minimum, but are not limited to, those activities associated with operation, maintenance, modification, and repair controls; the preparation, review, approval, and control of design changes, procurement documents, instructions, procedures, and drawings; receiving and plant inspections; indoctrination and training programs; the implementation of the operating and test procedures; and the remaining criteria in Appendix B to 10 CFR 50.

The results of each audit are reported in writing to the distribution delineated in accordance with station Technical Specifications. Additional internal distribution is made to other concerned management levels in accordance with approved procedures.

Management responds to all audits and initiates corrective action where indicated. Where corrective action measures are indicated, documented follow-up of applicable areas through inspections, review, re-audits, or other appropriate means is conducted to verify implementation of assigned corrective action.

I /

• 17.2-44

• J REVISION 23 12/94 SPS UFSAR If the Supervisor - Quality determines the response to an audit finding is unacceptable or if a finding response is not received in the time alloted or if corrective action for a finding is not accomplished as indicated on the response, the matter is brought to the attention of the Manager - Quality Assurance who notifies the Station Manager or appropriate Corporate Manager for resolution. If the Manager - Quality Assurance does not agree with the resolution proposed, he notifies the Manager' -

Nuclear Quality Assurance for referral to appropriate levels of management in accordance with established escalation procedures.

The responsibility for analyzing audit reports for trends and effectiveness lies with the Manager - Quality Assurance. As trends are discovered of if the effectiveness of the program is in question, the analysis of the Manager - Quality Assurance is forwarded to the management level consistent with the seriousness of the problem .

• 17.2-45

REVISION 23 12/94 SPS UFSAR APPENDIX A FIGURES NUCLEAR ORGANIZATION 17.2-46

APPENDIX A NUCLEAR ORGANIZATION FIGURE 17.2~1-1 Senior Vice President --- - - - - - - - - - Senior Vice President I MSRC 17.2.1.2.A.1 I

I Nuclear NOB 17.2.1.2.A.2 I Corporate Services 17.2.1.2.A I 17.2.1.2.E r,ecrelary to Senior Executive 1 I Regulatory Affairs I Advisor I Vice President Procurement 17.2.1.2.E I I I I Director Nuclear Vice President Nuclear Vice President Vice President Nuclear Manager Nuclear (

Administrative Operations Nuclear Services Engineering Services Quality Assurance *(

Services 17.2.1.2.G C 17.2.1.2.B 17.2.1.2.C 17.2.1.2.D 17.2.1.2.F

- A1el1lanl Va Prellldent Nucfea Operation*

- Manager Nudear Licensing and Programs 17.2.1.2.C.1

,_ Manager Nuclear Engineering 17.2.1.2.D.1 Manager Quality Assurance (Corporate)

_ Supervisor Managemenl Information and Plannln~

Ct

)

i 17.2.1.2.B.1 17.2.1.2.F.2

-L Station Manager Surry - Manager Nudear Training 17 .2.1.2.C.3 Manager Nuclear Electrical Enalneerlnq 17 .2.1.2.D.4

- Manager Quality l\ssurance (Surry) r 17.2.1.2.F.1 Personnel Administrator (Corporate) 17.2.1.2.B.2 Asslslanl Station Managers 17.2.1.2.B.2.a&b

- Manager Nuclear Business Services 17.2.1.2.C.4

._ Manager Nudear Analysis sind Fuel 17.2.1.2.D.2

- Manager Quality AHurance (North Anna) 17.2.1.2.F.1 i-Supervisor Nuclear Personnel Services Su1TV

-L Station Manager North Anna

._ Manager Nudear Materials 17 .2.1 .2.C.5

._ Manager ISI/NDE and Engineering Proarams 17.2.1.2.D.3 11111 Supervisor Nuclear Personnel Services North Anna 17.2.1.2.B.2 Assistant Station Managers 17.2.1.2.B.2.a&b

- Director Emergency PreparemeS11 17.2.1.2.C.2 Manager Clvll/Mechanlcal Engineering 17.2.1.2.D.4

- Manager Nucleu Operations Support

.17.2.1.2.B.3 17.2-47

APPENDIX A NUCLEAR STATION ORGANIZATION FIGURE 17.2.1-2 t------ ------ Manager Station Manager I SNSOC I I

Quality Assurance l

t 7.2.1.2.B.2.h 17.2. t .2.B.2 I 17.2.1.2.F. J I Secretary

~ Supervisors -

Quality I I I I C

(,

Assistant Station Superintendent Supervisor Assistant Station Superintendent Site (

Manager (O&M) Manager (NS&L) Services Radiological Administrative -,

Protection .Services (;

)

17.2.1.2.B.2.a 17 .2.1.2.B.2.b 17.2.1.2.B.2.c 17.2.1.2.B.2.d 17.2.1.2.B.2.e :i

- Superintendent Operations 17.2.1.2.B.2.a.1

- Supervisor Station Nuclear Safety (SNS) 17.2. 1.2.B.2.b. 1

- Superintendent Construction 17.2.1.2.B.2.c Superintendent Radwaste (Surry) 17.2.1.2.B.2.d

'1 Supervisor Shift Operations

• Supervisor Licensing Ila Supervisor Construction

• Engineering

... Supervisor Raclologlcal Engineering H 17.2.1.2.B.2.a. 1.1 17 .2.1.2.B.2.b.2 17.2.1.2.B.2.c 17.2.1.2.B.2.d Operation, Shift Supervisor Station Supervisor Supervisor Health Supervisor ProcedJres Construction Physics Technical 17.2.1.2.B.2.a. 1.2 Controls Services 17.2.1.2.B.2.b.3 17.2. t .2.B.2.c 17.2. 1.2.B.2.d

, AIIBlstant Shift Supervisor t 7.2.1.2.B.2.a.1.3 Superintendent

- Station COOfdlnator Emergency Planning t 7.2.1.2.B.2.b.4

- Supervisor Facllltles and Suooort 17.2.1.2.B.2.c Supervisor Health Physics Operations 17.2.1.2.8.2.d

~

Me!ntenance 17.2.1.2.B.2.a.2 - Envlronmental Compliance Coordinator - Supervisor Chemistry.

17.2.1.2.8.2.d

- Superintendent OUtage & Pl*mlng 17.2.1.2.B.2.b.5 17.2.1.2.8.2 .*.3

• .2-48

REVISION 23* 12/94 SPS UFSAR APPENDIX 8 TABLES

• 17.2-49

TABLE 17.2.0 Standard, Requirement or Guide Regulatory Gujde 1.8 - -Personnel Qualification and Training" (Second Proposed Revision 2, 9/80) Endorses ANSI/ANS-3.1 (Draft 12/79)

The applicability of this guide/standard lo other personnel in the Company organization is addressed in other sections of the UFSAR and the Technical Specifications of the Individual nuclear facility.

I The Company's Position Conformance Status Justification I.

The Operational Quality Assurance Program complies with Clarification and Alternative meet or exceed For Exception: NRC License Amendment this guide and standard, with one (1) exception, one (1) applicable guides and standar~s. Nos. 142 and 125 dated December 4, 1990 ( .

clarification and three (3) ahematlves. They are: for North Anna and NRC License Amendment Nos. 151 and 148 dated (1) Excegtjon: With regard to Section 4.2.2 of ANS 3.1 December 31, 1990 for Surry approved (Draft 12/79) titled Operations Manager. PaEagragh c. revisions to the Technical Specifications granting relief from Section 4.2.2 of ANS 3.1 Training: The Operations Manager will have or have held a senior operator license. (Draft 12/79). The exception allows the

(

Superintendent - Operations to hold .or have (2) ClarmcaUon: With regard to the term -aachelor's previously held a Senior Reactor Operator (.,

Degree* as used In the draft the following qualifications may License for the facility or a similar designed C be considered equivalent to a Bachelor's Degree: Pressurized Water Reactor plant. The

(

Supervisor Shift Operations will fuHill the )

A. 6 years of applied engineering experience at a rnclear Operations Manager requirements of ANS J facility in the area for which qualification is sought, 3.1 (Draft 12/79). This change allows the Superintendent Operations to perform

8. 6 years of operational or technical experience/training management functions and examine training related to engineering in nuclear power, and programs.

C. In addition, experience and training requirements For Clarification: ANSI/ANS - 3.1 (Draft shall be met as delineated. 12/79) does not provide a clear alternative to formal educational requirements, but does provide guidance. This guidance was

• utilized to develop clarification to qualify non-degree holding personnel.

50 '

• , 1986

TABLE 17.2.0 Standard, Requirement or Guide The Conyany*s Position Conformance Status JustHication (3) Artematjye: With regard to Section 4.4.5 of ANS 3.1 For Alternative: ANSI/ANS 3.1 1978.

(Draft 12/79) titled aua!tty Assurance. Paragraph 4.4.5 is considered to be consistent with the Company experience The Company will comply with Paragraph 4.4.5 as originally requirements which are delineated in other stated in ANSI/ANS 3.1 - 1978. areas of this report. Further, the 1978 .

(

requirement is considered more conservative than the Draft 12/79 ANS ~

Requirement.

(4) Altematjye: With regard to Section 4.3.2, Superyjsors For alternative: ANSI Section 4.3.2; Not Reguiring NRC License, Paragraph b: Experience: At Individuals having the specHied alternate the time of appointment to the posilion: the supervisor shall experience possess a working knowledge of have 4 years experience in the craft or discipline he plant activities (e.g., operations, (

supervises or an equivalent number of years nuclear plant maintenance, I & C, health physics, etc.) "1

(,

experience In a supervisory position with a Senior Reactor sufficient to perform a broad range of supervisory functions. The individual's day- C Operator's License. i to-day Interaction with the various plant (I

)

(5) Altematlye: With regard to Section 5.3.3 of ANSI/ANS activities has provided him with an  :,

3.1 (Draft 12179) titled Training lor ShlU Technical Advisor understanding of how each activity is integrated into safe and effective plant with Bachelor Degree without' an NBC Senior Operator operations. His combination of SRO training License, Section 3). The Shift Technical Advisors will and plant experience is adequate to assure observe control manipulations on the simulator as that actions performed by indivlduals under appropriate. his supervision are both technically correct and consistent with approved programs and procedures.

For atternatjye: ANSI section 4.3.2 (Draft 12/79): The performing of control manipulations Is not considered a Shift Technical Advisor task. The primary objective of ShHt Technical Advisor simulator instruction is IQ demonstrate plant and operator response to given conditions or events, not to develop expertise in control .

manipulations.

17.2-51 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde Reau1atoey Guide 1.26 - *Quality Group Classification and Standards for Water. Steam, and Radioactive Waste Containing Components of Nuclear Power Plants: (Rev. 3, 2/76).

The Con:J>any's Position Conformance Status Justification The Operational Quality Assurance Program complies with Clarification meets or exceeds applicable The Nuclear Design Control Program this guide with the following clarlflcatlon: guides and standards. standards provides the methodology and procedures for determining the quality The Company does not use the specific A, B, C, and D level classification of corrf)Onents. A specific classlficatlon system set forth In this guide. However, the listing of these components Is maintained in .

Company followed the requirements of this guide In a document called the a-List developing the list of structures, systems, and components for which the program Is applicable. The specific llsllng of

• Items lo which the Operational Quality Assurance Program (

applies Is desai>ed In detail In the 0-Llsl for Surry and North C Anna Power Stations. C

(

The Company also followed the requirements of this guide In )

developing the ASME Section XI Class 1, 2 and 3 J boundaries for the lnservlce Inspection and testing program.

These classes and boundaries are updated for each 1O year Inspection Interval.

• 52

, 1986

~

TABLE 17.2.0 Standard, ~equlrement or Guide Regulatory Guide 1.29 - *seismic Design Classification" (Rev. 3, 9/78)

The Conpany's Position Conformance Status JustHlcatlon The Operational Quality Assurance Program complies with ClarHication meets or exceeds applicable Regulatory Guide 1.29 Is primarily this guide with the following clarification: guides and standards. concerned with the design and construction phase of nuclear power plants. The See Generic Statement which prefaces this table with regard Company's clarHlcatlon has been fonnulated to construction related guides, standards and Instructions. to provide a means of translating design and oonstructlon criteria Into guidance applicable to operating nuclear power facilities.

(;

C "l

~

J 17.2-53 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde Regulatory Gujde 1.30 - *aualily Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment" (8/72). Endorses ANSI N45.2.4 - 1972.

The Corrpany's Position Conformance Status Justification The Operational Quality Assurance Program complies with Clarlflcatlons and atternatlves meet or These clarHicatlons to ANSI N45.2.4 - 1972 this guide with the following clarifications and attemallves: exceed applicable guides and standards. are required to ensure that QA program continuity Is mal.ntalned. In actuality these (1) See Generic Statement which prefaces this table with clarifications have been extracted from other regard to construction related guides, standards, and standards and guides and are considered instrucllons. more conservative. These clarifications also Insure that only one standard or guide Is (2) Section 2.1 - Planning requirements, as determined by committed to for its applicable circumstance.

station management. will be Incorporated Into maintenance (

and modification procedures. C

(

(3) Section 3 - Pceconstructlon VerHlcatlon: (a) verification Is required only for the modHlcatlon(s) (b) will be Implemented t

)

with the clarlflcatlon that *approved Instruction manuals* shall :i be Interpreted to mean the manuals provided by the supplier as required by the procurement order. These manuals will not be reviewed and approved, per se, by the Company; (c) no special checks will be made by the person withdrawing a replacement part from the warehouse-equivalent controls are assured by compliance with ANSI N45.2.2 as set forth in this table; and (d) will be complied with, as determined by station management as part of the maintenance/modification

-program.

54

• e, 1986

TABLE 17.2.0 Standard, Requirement or Guide The Conpany*s Position Conformance Status JustHlcatlon Section 4 - lnstaHatlon: instructions will be i"l)lemented by inclusion, as determined by station management, in the appropriate maintenance or modHicatlon procedure for safety related items. Standard Company maintenance practices require that care be exercised In the six areas listed whether (

a procedure Is required or not. J Section 5.1 - tnspecUons: including subsections 5.1.1, 5.1.2, and the first sentence n 5,1-.3, will be implemented as set forth In Section 17 .2.1 O of the Operational QA Program. The inspection program will incorporate, as determined by station management, those (

hems listed In these subsections. The remaining sentence (

In 5.1.3 Is covered In equivalent detail In the Company's C

commitment to ANSI N18.7, section 5.2.6; the requirements *;

as set forth In that commitment will be Implemented in addition to the requirements stated here.

~

J Section 5.2 - I.e.sa: Including subsections 5.2.1 through 5.2.3, wlll be Implemented as set forth In Sections 17.2.3 and .11 of the Operational QA Program. The test program will consider the elements outlined in this Section, as determined by station management, when developing

_test requirements for Inclusion in maintenance and modification procedures. In some cases, testing requirements may be met by post-installation surveillance testing in lleu of a special post-Installation test. Where elements of Section 5.2 are not being met they shall be documented and justified. -

17.2-55 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde The CoRJ>any*s Position Conformance Status Justification Section 6

• Post Construction Yerllication: Is not generally considered applicable at operating facilities because of the scope of work and the relatively short Interval between Installation and operation. Where considered necessary by station management, the elements described In this section will be used In the development and implementation of Inspection and testing programs as described In Sections 17.2.3, .10, and .11 of the Operational QA Program.

Section 6.2.1 - EQJpnent Tests: The last paragraph of this section deals wHh tagging and labeling. The Company C wlll comply wfth an ahemate last paragraph which reads: (

• each safety-related Item of process Instrumentation is (

Identified with a unique number. This number Is utilized In

(,

Instrument maintenance records so that current calibration )

status, Including data such as the date of the calibration and  :,

Identity of the person that performed the calibration, can be readily determined. Such Information may also be contained on tags or labels which may be attached to Installed Instrumentation*.

Section 7 - Data Analysis and Evaluation: will be Implemented as staled herein after adding the clarifying phrase "when determined by station management" at the beginning of that paragraph.

56

• , 1986

TABLE 17.2.0 Standard, Requirement or Guide Regulatory Gujde 1,33 - "Quality Assurance Requirements (Operation)" (Rev. 2, 2/78) - Endorses ANSI N18.7 - 1976.

The Conpany's Position Conformance Status Justification The Operational Quality Assurance Program complies with Clarifications and alternatives meet or These clarifications are required to ensure this guide with the following clarifications and alternatives: exceed applicable guides and standards. that QA program continuity is maintained; I.e., that only one standard or guide ls

1) Paragraph C.3 rsubjects Requiring Independent committed to for a particular topic.

Review*) of Regulatory Gulde 1 .33 (and Section 4.3.4 of ANSI N18.7 - 1976 which It references) will be Implemented as required by the applicable nuclear facility Technical SpecHlcatlons, Emergency Plan, Security Plan, and Fitness for Duty Program which designate the areas subject lo Independent reviews.

(

2) Paragraph C.4 (*Audit Program*) of Regulatory Gulde (

1.33 (and Section 4.5 of ANSI N18.7

• 1976 which ii C references) will be Implemented as required by the applicable nuclear facility Technical Specifications, C

)

.Emergency Plan, Security Plan, Fitness for Duty  ::

Program, and administrative controls which designate the minimum areas to be audited. The audit program Is further defined and will be Implemented as required by the commitment to ANSI N45.2.12 as stated In Table 17.2.0 of the Operatlonal Quality Assurance Program.

Paragraph C.4.c of Regulatory Gulde 1.33 (and ANSI N18. 7 to which It references) will be Implemented as clarified In Section 17.2.18 of the Operational Quality Assurance Program Topical Report. Specifically, the frequency for conducting audits of the performance,

-training, and qualHicatlons of the facility staff may vary based on performance and the safety significance of the audited activity but will not be less frequent than biennial (2 YE!ars).

3)

• Paragraph C.5a of Regulatory Guide 1.33 (and Section 4.4 of ANSI N18. 7 which It references) will be implemented with the clarification that the Station Nuclear Safety and Operating Committee may perform this activity.

17.2-57 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde The Conpany's Position Conformance Status JustHlcallon

4) Paragraph C.5.d of Regulatory Gulde 1.33 (and Section 5.2. 7.1 of ANSI N18. 7 which It references) will be Implemented by adding the clarifying phrase "When determined by station management In front of the fourth sentence of the fHth paragraph. For modHlcatlons where these requirements are not considered practicable, a review In accordance with the provisions of 10CFR50.59 shall be conducted and documented.

5) Paragraph C.5.e of Regulatory Gulde 1 .33 (and Section 5.2.13.4 of ANSI N18.7 which It references) will be Implemented subject to the same clarlf lcatlons made for C ANSI N45.2.2 elsewhere In Table 17.2.0 of the (

Operatlonal QA Program. C

6) Paragraph C.5.f of Regulatory Gulde 1.33 (and Section t

)

5.2.19.(2) of ANSI N18.7 which It references) will be  :;

Implemented when determined by station management.

7) Paragraph C.5.g of Regulatory Gulde 1.33 (and Section 5.2.19.1 of ANSI N18.7 which It references) will be Implemented with the addition of the modifier "normally" after each of the verbs (should) which the Regulatory Gulde converts to "shall." II Is the Company's Intent to fully comply with the requirements of this paragraph, and any conditions which do not fully comply will be documented and approved by station management personnel. In these areas, the reason for the exception shall also be documented. The documentation shall be retained for the same period of time as the affected preoperatlonal test.

.58 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde The Conpany's Position Conformance Status Justification

8) With regard to*sectlon 4.2 of ANSI N18.7 - 1976 titled Program Descr11Uon: Two aspects are addressed In this Section: audits and Independent reviews. The Independent review program Is Implemented as required by the Technical Specifications of the Individual nuclear t facility. The Company audit program will be described In J accordance with and to meet the requirements of ANSI N45.2.12 as endorsed In Table 17.2.0 of the Operational QA Program, the requirements of the Individual nuclear facility Technical Specifications, and Sections 17.2.16 and 17.2.18 ~f the Operational QA Program.

C

(,

9) With regard to Section 4.3 of ANSI N18.7 - 1976 titled C

Independent Review Process: The requirements of this Section, Including all of Its subparts, shall be met by '

(j

)

compliance with the Technical Specification J requirements of the Individual nuclear facility.

10) With regard to Section 5.2.2 of ANSI 18.7 - 1976 titled The requirement to have the supervisor In Procedure Adherence: The third and fourth sentences charge of the shift (Shift Supervisor) of the first paragraph of the Section address approval awrove non-Intent changes to procedures requirements for temporary changes to procedures Is 'deleted. Administrative procedures which do not change the Intent of the approved ensure that non-Intent procedure changes procedure. For North Anna, adequate reviews will be have minimal, If any, Impact on station provided by two members of the plant supervisory staff operations. The current approval process knowledgeable In the areas affected, one of which will unnecessarily distracts the Shift hold a senior operator license on the unit affected. For SupervlsQr's attention away from ongoing Surry, adequate reviews will be performed In accordance station operations.

with the Technlal Specifications.

17.2-59 June. 1986

TABLE 17.2.0 Standard, Requirement or Gulde The Corrpany's Position Conformance Status Justification

11) With regard to Section 5.2.7 of ANSI N18.7-1976 titled Maintenance and ModHlcation: Since some emergency situations could arise which might preclude preplanning of all activities, the Company will co"1)1y with an alternate to the first sentence In the second paragraph which reads: *Except In emergency or abnormal operating conditions where Immediate actions are required to protect the health and safety of the public, to protect equipment or personnel or to prevent the deterioration of plant conditions to a possibly unsafe or unstable level, maintenance or modification of equipment shall be preplanned and performed In accordance with written (1 procedures. Where written procedures would be (

required and are not used, the activities that were (

accomplished shall be documented after-the-fact and -,

receive the same degree of review as 11 they had been Ci

)

preplanned.*  :,

12) With regard to Section 5.2.7.1 of ANSI N18.7 - 1976 titled Maintenance programs: The Company will comply with the requirements of the first sentence of the fifth paragraph, when determined by station management.

This clarification Is needed since It Is not always possible to promptly determine the cause of the malfunction. In all cases, the Company will Initiate proceedings to determine the cause, and wlll make such determinations promptly, when determined by station management.

13) With regard to Section 5.2.8 of ANSI N18.7 - 1976 tilled Surveillance Testing and Inspection Schedule: In lieu of a "master surveillance schedule," the following requirement shall be compiled with:

• A surveillance testing schedule(s) shall be established reflecting the status of all in-plant surveillance tests and inspections."

14) With regard to Section 5.2.13.1 of ANSI N18.7 - 1976 tilled Procurement Document Control: The words "the same degree of control" in the last sentence are replaced with ~Engineering review."

60

• , 1986

TABLE 17.2.0 Standard, Requirement or Gulde The CorTJ)any*s Position Conformance Status JustHlcatlon

15) With regard to Section 5.2.15 or ANSI N1B.7 - 1976 titled The biennial review requirement Is deleted.

Review. Aogmval and Control of Procedures: The third The procedures upgrade program provides sentence In paragraph three Is inierpreted to mean: a systematic and effective process for Applicable procedures, as. determined by Station developing and revising procedures ~hich Management. shall be reviewed following an accident, an encompasses the Intent of the biennial unexpected transient, significant operator error or review.

equipment malfunction.

The first sentence of the fourth paragraph Is considered to be met via procedure reviews as described by administrative procedures.

(

16) With regard to Section 5.2.17 of ANSI N18.7 - 1976 titled t Inspections: Nol all Inspections will require generation of C a separate Inspection report. Inspection requirements -,

(/

may be Integrated Into appropriate procedures or other )

documents with the procedure or document serving as  ::i the record. However. records of Inspections will be identifiable and retrievable.

17) With regard to Section 5.3.9 of ANSI N18.7 - 1976 titled Emergency Procedure: As directed by the NRC, the Company follows a format for emergency procedures which Is "symptom" based as opposed to "event" based as stipulated In Section 5.3.9.1. Since the Co"1)any has these "symptom" based procedures; "event" based procedures are not normally provided. .

17.2-61 June. 1986

TABLE 17.2.0 Standard, Requirement or Gulde The Corrpany's Position Conformance Status Justification

18) With regard to Section 5.3.9.2 of ANSI N18.7 - 1976 titled Events of Potential Emergency: The Company will I

(*

interpret item (11) to mean the natural occurrences which have been evaluated In the UFSAR for the Individual nuclear facility.

19) With regard to Section 5.3.9.3 of ANSI N18.7 - 1976 titled Procedures for lmptementlng Emergency Plan:

The Company's NRC accepted Emergency Plan for each nuclear facllhy will be Implemented In* lieu of the requirements In this Section.

{

(

{

i (I

)

i 62 .

• , 1986

TABLE 17.2.0 Standard, Requirement or Gulde NRC Regulatory Guide 1,37 - "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled

..;.N.;.;;u;...;;;cl;...;;;e~ar_P_o_w_e""-r..;.P....;;la-n_ts_*_._t3-/_73"")_-_E-ndo..;;;..;;..r_s_e.;a.s__

A__N_S_I_N_45-._2_.1_-_1__9_7_3_.- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - c

(

The Conpany's Position Conformance Status JustHlcatlon '

The Operational Quality Assurance Program complies with Clarifications meet or exceed applicable The four clarifications listed were generated this guide with the following clarHlcations: guides and standards. to translate general guidance Into exact -t commitments, and to provide alternate

1) The guide and standard are applicable to those areas of means to perform routine tasks. ~

the Quality Assurance Program addressing on-site cleaning of materials and components, cleanness control, and preoperatlon cleaning and layup of fluid systems.

2) With regard to Paragraph C.3 of Regulatory Gulde 1.37: (,

The water quality for flnal flushing of fluid systems and (,

associated componen1ls shall be at least equivalent to C the quality of the operating system water except for the -,

oxygen and nitrogen content: but this does not Infer that chromates or other additives, normally In the system water, will be added to the flu.sh water.

3) With regard to Paragraph C.4 of Regulatory Gulde 1.37:

Expendable materials such as Inks and related products, temperature Indicating stick, tapes, gummed labels, wrapping materials (other than polyethylene), water soluble dam materials, lubricants, NDE penetrant materials and couplants, desiccants, and Ilka materials which contact stainless steel or nickel alloy surfaces: shall not contain lead, zinc, copper, mercury, cadmium and other low melting point metals, their alloys or compounds as basic and essential chemical constituents. No more than 0.1 percent (1,000 ppm) halogens will be allowed where such elements are leachable or where they could be released by breakdown of the compounds under expected environmental conditions.

17.2-63 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde NAC Regulatory Gujde 1.37 - "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants* (3/73) - Endorses ANSI N45.2.1 - 1973.

The Corrpany's Position Conformance Status JustHicatlon

4) With regard to Section 5 of ANSI N45.2.1 - 1973 titled lostaHation Cleaning: The recommendation that local rusting on corrosion resistant alloys be removed by mechanical methods Is interpreted to mean that local rusting may be removed mechanically, but the use of other removal means Is not precluded as determined by Engineering.

(

(.

C (i

)

J

.64 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde NRC Regu!atQO' Guide 1.38 - *Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled

..;.N_u""'cl""'e_ar-P_o-w.;,,;e_r-P_la-nt_s'-*....tR_e_v_. ..;;;;2~,5.;;.;./7..;,,7...,)._-_E.;;.;.nd-""'o.;..;;rs;.,.;;.e""'s-A'-N;,.;;Sa...l-N'-4""'5.""2~.2'---1;,.;;9_7-2_.- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 The CorYJ>any's Position Conformance Status Justif lcatlon .

(

The Operational Quality Assurance Program complies with Clarifications and alternatives meet or The clarifications In this section are this guide with the following clarifications and alternatives: exceed applicable guides and standards. proposed only to translate general guidance .

[

Into specHlc requirements. (J

1) With regard to Section 2.1 of ANSI N45.2.2 - 1972 titled J Planning: (First sentence.) The specHlc items to be The proposed alternatives are provided to governed by the Standard shall be ldentlf led In reflect current Company practices which are Administrative Procedures. distilled from over ten years of experience gained at operational nuclear facllltles.

2) With regard to Section 2.3 of ANSI N45.2.2 - 1972 titled Results: The specific methods for performing and (,

documenting tests aoo Inspections are given In Sections (,

17.2.10 and 17.2.11 of the Operational QA Program. C The requirements In these Sections will be Implemented In lieu of the general requirements here. )

ti

J

3) With regard to Section 2. 7 of ANSI N45.2.2 - 1972 titled Clarification of Items: The Company may choose not to explicitly use the four level classification system.

However, the specific requirements of the Standard that are appropriate to each class are applied to the Items suggested In each classHlcatlon and to slmilar Items as determined by station management.

4) With regard to Section 3.2.1 of ANSI N45.2.2 - 1976 titled Level A Items: As an alternate to the requirements for packaging and containerizing Items in storage to control contaminants (Items (4) and (5)), the Company may choose 17.2-65 June, 1°986

TABLE 17.2.0 Standard, Requirement or Gulde The Conyany's Position Conformance Status Justification a storage atmosphere which Is free of harmful contaminants In concentrations that could produce damage to stored Items as determined by station management. Similarly (for Item (7)) the Company may obviate the need ror caps and plugs, as determined by station management, with an appropriate storage atmosphere, and may choose to protect weld-end preparations and threads by controlling the manner In which the Items are stored. These clarHlcatlons apply whenever Items (4), (5) or (7) are subsequently referenced and to Section 3.5.1 lltled Caps and Plugs and Section 3.4 titled Methods 01 Pceseryalion. C

(

5. With regard to Section 3.2.3 of ANSI N45.2.2 1972 titled Level c Items: (Subpart 2) states *1tems shall be {

(;

packaged with a waterproof enclosure . . . ,* as an )

alternative, the company may choose appropriate  ::i packaging when the storage environment prevents harmful contaminants In concentrations that could produce damage to stored Items as determined by Station mgrnt.

6) With regard to Section 3.3 of ANSI N45.2.2 - 1972 titled Cleaning: (Third sentence) the Company Interprets

• documented cleaning methods* to allow generic cleaning procedures to be written which are Implemented, as necessary, by trained personnel. Each particular cleaning operation shall have an Individual cleaning procedure or reference a generic procedure .

. The generic procedures will specify methods of cleaning or which type(s) of solvent may be used In a particular application.

66

• , 1986

TABLE 17.2.0 Standard, Requirement or Gulde The Company's Position Conformance Status Justification

7) With regard to Section 3.4 of ANSI N45.2.2 - 1972 titled Methods of Preservation: (First sentence) the Company ,.

(

will comply with these requirements subject to the clarifications of Section 3.2.1, (4) and (5) above, and the definition of the phrase "deleterious corrosion" to mean l that corrosion which cannot be subsequently removed .I and which adversely attects form, fit or function.

8) With regard to Section 3.6 of ANSI N45.2.2 .* 1972 titled Barrier and Wrap Material and Desiccants: This section requires the use of nonhalogenated materials In contact with austenltic stainless steel. Refer 10 Regulatory Gulde (

1.37 above for lhe Company position.

t

(

9) With regard to Section 3.7.1 of ANSI N45.2.2 - 1972 titled -,

Containers: Cleated, sheathed boxes may be used up C,

)

to 1,000 lbs. rather than 500 lbs. as specified In 3.7.1(1).  :,

This lype of box Is safe for, and has been tested for, loads up to 1,000 lbs. Other national standards allow this (see Federal Specification PPP-B-601 ). Special qualifications testing shall be required for loads above 1,000 lbs.

10) With regard to Section 3.7.2 of ANSI N45.2.2 - 1972

• titled Crates and Skids: Skids or runners will normally be used on containers with a gross weight of 100 lbs. or more. Skids or runner will normally be fabricated from*4 x 4 inch nominal lumber size, minimum, and lald flat except where this is impractical because of the small dimensions of the container. If forklift handling Is required, minimum floor clearance for forklift tines will be provided.

17.2-67 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde The Conyany's Position Conformance Status JustHlcallon

11) With regard lo Sections 4.3, 4.4 and 4.5 of ANSI N45.2.2

- 1972 titled, respectively, Precautions During Loading and Transit. ldenuncauon and Marking. and Shipment from Countries outside the United States: The Company will comply with the requirements of these Sections subject to the clarHlcallons taken to other Sections which are referenced herein.

12) With regard to Section 5.2.1 of ANSI N45.2.2 - 1972 titled Shipping Damage lnsgeclion: Warehouse personnel will normally visually scruUnlze Incoming

(

shipments for damage or the types listed In this Section:

this activity Is nol necessarily performed prior lo (

unloading. Since all required Items receive the Item C Inspection or Section 5.2.2, separate documentation of -,

(.,

lhe Shipping Damage Inspection Is not necessary. )

Release of the transport agent afler unloading and :i signing for receipt of lhe shipment may be all of the action taken lo document completion of lhe Shipping Damage Inspection. Any noncontormance noted will. be documented and dlsposltloned as required by Section 17.2.15 of the Operational QA Program.

The person performing the visual scrutiny during unloading Is not considered to be performing an Inspection function as defined under Regulatory Guide 1.74; therefore, while he will be trained to perform this function he may not necessarily be certHied (N45.2.6) as an Inspector.

J 68 I 1986

~

TABLE 17.2.0 Standard, Requirement or Gulde The CoRJ>any*s Position Conformance Status Justification

13) With regard to Section 5.2.2 of ANSI N45.2.2 - 1972 titled Uem lospectlpn: The second division of this subsection requires six additional Inspection activities if an item was not Inspected or examined at the source.

Procurement Engineering shall determine and document the extent of receipt Inspection based on consideration of Paragraph 5.2.2. *

14) With regard to Section 5.4 of ANSI N45.2.2 - 1972 titled Status Indicating System: The Section states In part NTags shall be securely affixed to the hems and displayed In an area that Is readily accessible.* As an alternative, the company may choose to use Labels or Tags to Identify hems. C

(;

15) With regard to Section 6.1.2 of ANSI N45.2.2 - 1972 )

• titled Levels or Storage: Subpart (2) Is replaced with the J following:

(2) Level B Items shall be stored within a fire resistant, weather-tight, and well ventilated bulldlng or equivalent enclosure In which measures have been taken against vandalism. This building shall be situated and constructed so that It will not normally be subject to flooding; the floor shall be paved or equal, and well drained. If any outside waters should come In contact with stored equipment,* such equipment will be labeled or tagged nonconforming, and then the nonconformance document will be processed and evaluated In accordance with Section 17.2.15. Items shall be placed on pallets, shoring or shelves to permit air circulation. The building shall be provided with uniform heating and temperature control or Its equivalent to prevent condensation and co*rroslon. Minimum temperature shall be 40°F and maximum temperature shall be 14Cl°F or less if so stipulated by a manufacturer.

17.2-69 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde The ConJ>any*s Position Conformance Status Justification

16) With regard to Section 6.2.1 of ANSI N45.2.2 - 1972 titled Access to Storage Areas: Items which fall within the Level D classiflcatlon of the standard will be stored In an area which may be posted to llmlt access, but other positive controls such as fencing or guards wlll not (

normally be provided. J

17) With regard lo Section 6.2.4 of ANSI N45.2.2 - 1972 lilied Storage of Food and Associated Items: The sentence Is replaced with the following: "The use or storage of food, and drinks In any storage area shall be controlled and shall be llmlled to designated areas where C such use or storage Is not deleterious lo stored items (

where station management deems appropriate.

(

18) With regard lo Section 6.2.5 of ANSI N45.2.2 - 1972 (i

)

lilied Measures to Prevent Entrance of Animals: The  :;

sentence Is replaced with th.e lollowlng: "Exterminators or other appropriate measures shall be used to control animals to minimize possible contamination and mechanical damage to stored material."

70

• , 1986

TABLE 17.2.0 Standard, Requirement or Gulde The Company's Position Conformance Status Justlf lcation

19) With regard 10* Section 6.3.4 of ANSI N45.2.2 - tilled Identification: The section stales *An items and their containers shall be plainly mar1<ed so that they are easily identified without excessive handling or unnecessary opening of crates and boxes: The company shall substitute *All Items (or, if in containers, their containers) shall be plainly mar1<ed so that they are easily Identified without excessive handling or unnecessary opening of crates and boxes.*

20) With regard _lo Section 6.4.2 of ANSI N45.2.2 - 1972 titled Care ol Hems: The following ahernallves are (

provided for the Indicated subpart: (

(

(5) *space heaters In electrical equipment shall be

(

energized unless a documented engineering )

evaluation determines that such space heaters are J not required.*

(6) *Large (greater than or equal to 50HP) rotating electrlcal equipment shall be given Insulation resistance tests on a scheduled basis unless a documented engineering evaluation determines that such tests are not required.*

(7) -Within thirty days of having been placed in storage, rotating equipment weighing over approximately 50 pounds shall be evaluated by engineering personnel to determine if shaft rotation in storage Is required: The results of the evaluation shall be documented. If rotation Is required, it shall be performed at specific intervals, be documented, and be conducted so that parts receive a coating of lubrication where applicable and so that the shatt does not come to rest In the same position occupied prior lo rotation. For long shafts or heavy equipment subject to undesirable bowing, shaft orientation atter rotation shall be specified and obtained.

17.2-71 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde The Colll)any's Position Conformance Status Justification

21) With regard to Section 6.5 of ANSI N45.2.2 - 1972 titled Removal of Items from Storage: The Colfl)any does not consider the last sentence of this Section to be applicable to the operations phase due to the relatively short period of time between Installation and use. The (

first sentence of the Section Is replaced with: "the ' J Company will develop, Issue, and Implement a procedure(s) which cover(s) the removal of Items from storage. The procedure(s) will assure that the Inspection status of all material Issued Is known, controlled and appropriately disposltloned .-

(

22) With regard to Section 6.6 of ANSI N45.2.2 - 1972 titled (

Storage Records: The Co111>any will comply with the (

requirements of this Section wfth the clarification that, for

(,

record purposes, only the access of personnel not )

specifically authorized such by station management Into  ;:;

Indoor storage areas shall be recorded. Unloading or pick-up of material shall not be considered "access," nor shall Inspection by QA/QC personnel, authorized contractors, NRC or other regulatory agents, nor shall tours by non-employees.

.72*

June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde The Conpany's Posttlon Conformance Status JustHlcatlon

23) Wtth regard to Section 7.3 of ANSI N45.2.2

• 1972 titled Hoisting Equipment: Aerating of hoisting equipment will I

.t be considered only when absolutely necessary. Prior to performing any lift above the load rating, the equipment manufacturer must be contacted for his approval and direction. The manufacturer must be requested to supply a document granllng approval for a limited number of lifts at the new rating and any restrictions Involved, such as modifications to be made to the equipment, the number lifts io be made al the new rating, and the test lift load. Al all times, the codes governing reratlng of hoisting equipment must be (

observed. (,

C If reratlng hoisting equipment Is necessary and the Company cannot or does not contact the equipment (;'

)

manufacturer as described above, the test weight used :J In temporarlly reratlng hoisting equipment for special IHts will be at least equal to 110% of the rrrt weight. A dynamic load test over the full range of the lift using a weight at least equal to the IHI weight shall be performed.

24) With regard to Section A3.9 of ANSI N45.2.2 - 1972 tttled Marking: As an alternative to the requirements In Subpart 4, the Co"1)any may choose to mark containers with waterproof Ink or paint with legible characters.

Additionally, the requirements of Subpart 6 shall only apply to shipment of Items. Items In storage shall be affixed with labels or tags with sufficient Information to preserve the item's Identity.

17.2-73 June, 1986

TABLE 17.2.0 Standard, Requirement or Guide NRC Regu!atog Guide 1,39 - "Housekeeping Requirements for Water-Cooled Power PlahtsN (Rev. 2, 9/77) - Endorses ANSI N45.2.3-1973.

The CorTJ>any's Position Conformance Status Justification I

The Operational Quality Assurance program complies with Clarifications meet or exceed applicable These clarifications are proposed to perform I' this guide with the following clarifications: guides and standards. a twofold function.

See Generic Statement which prefaces this table.

• A) To translate construction criteria to (

_I operating plant oriented

1) Additional clarifications for ANSI N45.2.3 - 1973 are requirements.

Indicated below for specific Sections.

B) To reflect experience gained at Section 2.1 P!aooloo: The Company may choose operational nuclear facilities.

not to utilize the five-level zone designation system,

(,

but will utilize standard janltorlal and work practices to It should be noted that where the Company -,

maintain a level of cleanliness as delineated In the does not specifically Implement C:

Company's Accident Prevention Manual which Is requirements as delineated herein, the C equlvalent to the requirements contained In the proposed alternatives are reflected In written

(

referenced section. procedures and policy and contain all )

necessary elements to assure quality Is Cleanliness will be maintained, consistent with the maintained.

• work being performed, so as to prevent the entry of foreign materlal into safety-related systems. This will Include, as a minimum, documented cleanliness Inspections which will be performed prior to system closure.

As determined by station management, (e.g., the size of the opening would permit entry of the tools being used) control of personnel, tools, equipment, and supplies will be established when the reactor system Is opened for Inspection, maintenance or repair.

Additional housekeeping requirements will be implemented as required for control of radioactive contamination.

s 74 J

• e, 1986

TABLE 17.2.0 Standard, Requirement or Gulde Ttie Conpany's Position Conformance Status Justlflcatlon Section 2.2 - Procedures and lnstrucuons:

Appropriate procedures will be written and Implemented .

. Section 3.2

• Control of FacHIUes: The Corf1)any may choose not to utilize the five-level zone designation system, but wlll utilize the Company's Accident Prevention Manual pollcles and procedures to maintain a level of cleanliness commensurate with the requirements of this section.

Cleanliness will be maintained, consistent with the (,

wor1< being performed, so as lo prevent the entry of (,

foreign material Into safety-related systems. This wlll C Include, as a minimum, documented cleanliness "i (I

Inspections which will be perfonned prior to system )

closure. As necessary, (e.g., the size or the opening  ::i would .pennll entry or the tools being used) control or personnel, tools, equipment, and supplies wlll be established when major portions or the reactor system are opened for Inspection, maintenance or repair.

Additional housekeeping requirements wlll be Implemented as required for control or radioactive contamination.

Section 3.3 - Materials and Egujpment: See Generic Statement which prefaces*thls table.

Section 3.4 - Construction Tools, Supplies and Egujpment: See Generic Statement which prefaces this table.

section 3.5 - survemance, laspecUons and Examlnation: Subparagraph (1) See Generic Statement which prefaces this table.

17.2-75 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde NRC Reguiatoey Guide 1.58 - Qualification or Nuclear Power Plant Inspection, Examination and Testing Personnel" (Rev. 1, 9/80) -

Endorses ANSI N45.2.6 - 1978.

The Corrpany's Position Conformance Status JustHlcatlon The Operational QA Program complies with this guide with Clarifications meet or exceed applicable The proposed clarHlcations reflect Company the following clariflcatlons: guides and standards. practices and are provided here to assure I*

j that QA program continuity with other

1) With regard to Section 1.2 of ANSI N45.2.6 - 1978 titled delineated standards and guides Is AppUcab!Hly: The third paragraph requires that the maintained.

Standard be used In conjunction with ANSI N45.2; the Company no longer specifically commits to ANSI N45.2 In the Operational QA Program. The fourth paragraph

(

requires that the Standard be Imposed on personnel other than Company employees; the applicability of the (,

Standard to suppliers will be documented and applied, (

as appropriate. In the procurement documents for such

(.

suppliers. )

J

2) With regard to Section 1.4 of ANSI N45.2.6 - 1978 titled Definitions: Definitions In this Reg. Gulde 1.58 which are not Included In ANSI N45.2.10 will be used: all definitions which are Included In ANSI N45.2.10 will be used as clarified In the Company's commitment to Regulatory Gulde 1.74.

3) With regard to Section 2.5 of ANSI N45.2.6 - 1978 titled Physical: The Company will Implement the requirements of this Section with the stipulation that, where no special physical characteristics are required, none will be specified. The converse Is also true: If no special physical requirements are stipulated by the Company, none are considered necessary.

4) With regard to Section 3.1 of ANSI N45.2.6 - 1978 titled General: The Company will Implement the requirements of this Section with the stipulation that, Level Ill Inspectors are not a specific requirement of the Company's Inspection program.

• -76

, 1986

TABLE 17.2.0 Standard, Requirement or Gulde NRC Regulatory Guide 1.64 - "Quality Assurance Requirements for the Design of Nuclear Power Plants" (Rev. 2. 6176) -

Endorses ANSI N45.2.11 - 1974.

The CorT!)any*s Position Conformance Status JustHicatlon The Operational Quality Assurance Program complies with ClarHication meets or exceeds applicable Clarification is considered an acceptable this guide with the following clarification:

• guides and standards. . alternative to that proposed In the referenced standard In that all quality See Generic Statement which prefaces this table. elements have been maintained.

1) With regard to Paragraph C.2(1) of Regulatory Guide 1.64: If In an exceptional circumstance the designer's Immediate Supervisor Is the only technically qualified lndlvlwal available. this review may be conducted by the C Supervisor. providing that: (a) the other provisions of (

the Regulatory Gulde are. satisfied, and (b) the C

justification Is Individually documented and approved In advance by the Supervisor's management. and (c) (

)

quality assurance audits cover frequency and J ettectlveness of use of Supervisors as design verifiers lo guard against abuse .

17.2-77' June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde NBC Regu!atocy Guide 1,74 - "Qualtty Assurance Terms and Definitions" (2/74) - Endorses ANSI N45.2.10-1973.

The Corrpany's Position Conformance Status Justification The Operational Quality Assurance Program complies with Clarification meets or.exceeds applicable The clarifications illuminate actual Cofll)any this guide with the following clarification: guides and standards. QA program practices and are considered to enhance the Company's commitment to

1) The Company reserves the right to define additional quality practices.

words or phrases which are not Included In this Standard.

Such additional definitions will be documented In appropriate procedures and/or In attachments/appendices lo a quality assurance procedures manual or In sections of the Operational QA Program.

(

2) The Company Intends for Inspections and tests lo be (

performed In accordance with the Operational QA C Program by personnel certified as required by that

(,

program and for activities defined by *inspection* and )

• Testing* In ANSI N45.2.10. Appropriate references to :i the organization which will perform the activity or quality procedures to be used for performing the activity will be made. If such references are not made. Inspections or tests are to be considered under the following definition:

"Inspection* (when used to refer to activities that are not performed by certified personnel) - Examining, viewing closely, scrutinizing, looking over or otherwise checking activities. Personnel performing these functions are not necessarily certHled to ANSI N45.2.6. However, station management through prior procedure review shall determine the appropriate personnel qualifications and reporting relationships.

"Testing" (when used lo refer to activities that are not performed by certified personnel) - completion of predetermined procedure steps which determine or verify the capability of an item to meet specified requirements by subjecting the Item to a set of physical, chemical, environmental, or operating conditions.

Personnel performing these slaps may nQl necessarily be certified to ANSI N45.2.6. If the completion of the

• • 78 June, 1986

TABLE 17.2.0 Standard, Requirement or Guide The Corrpany's Position Conformance Siatus Justification procedural steps utilizes skills and knowledge wtJlch they I*

have already obtained from applicable training and (

experience based programs or formal education programs. Station management through prior procedure -

review shall determine the appropriate personnel t qualifications and repor11ing relationships. ~

3) In addition to the Standard's definition of "procurement documents,* the Company will utilize the* definitions given in ANSI N45.2.13 and In Regulatory Guide 1.74.

The compound definition Is given as follows:

Procurement documents - Contractually binding (;

1 documents that Identify and define the requirements (I which Items or services must meet in order to be C

considered acceptable by the purchaser. They include -:

documents which authorize the seller to perform (I

)

services or supply e"'lpment, material or facilities on :J behaH of the purchaser (e.g., contracts, letters of Intent, work orders, purchase orders or proposals and their acceptance, drawings, electronic procurement system documents, specifications or instructions which define requirements for purchase).

4) "Program Deficiencies* (Not defined In ANSI N45.2.10, but used and defined differently In ANSI N45.2.12) -

Failure to develop, document or Implement effectively any applicable element of the Operational QA Program.

5) "Quality Assurance Program Requirements" (Not defined In ANSI N45.2.10 but used and defined differently in ANSI N45.2.13) - Those individual requirements of the Oper.ational QA Program which, when invoked in total or in part, establish the requirements of the quality assurance program for the activity being controlled.

Although not specially used In the Operational QA Program, ANSI N45.2 may be Imposed upon the Company's suppliers .

17.2-79 June, 1986

TABLE 17.2.0 Standard, Requirement or Guide The Con1)any's Posttion Conformance Status JustHication

6) With the exception of the time intervals defined by the station Technical SpecHicalions, the following definitions shall be applied when defining time intervals for other activities:

Weelsly: at least once per 7 days Month!y: at least once per 31 days Quarterly or every 3 months: at least once per 92 days SemlanwaHy or every emonths: at least once per 184 (

days (

(

Every 9 months: at least once per 276 days t

)

Vearty or annual!y: at least once per 366 days  :,

Biennial (2 years): at least once per 732 days Triennial (3 years): at least once per 1098 days The above time intervals may be extended by up to 25% .

TABLE 17.2.0 Standard, Requirement or Guide NRC Regulatory Guide 1.BB - "Collection, Storage and Maintenance of Nuclear Power Plant Quality Assurance Records" (Rev. 2, 10/76 -

Endorses ANSI N45.2.9 - 1974).

The CoOJ)any's Position Conformance Status JustHlcation The Operational Quality Assurance Program complies with Clarifications and alternatives meet or These proposals are the results of this guide with the following dariflcatlons and alternatives: exceed applicable guides and standards. experience gained at operating nuclear facilities for over a decade. As with all guides

1) With regard to Section 3.2.2 of ANSI N45.2.9 - 1974 titled and standards, additlonal clarity Is sometimes lruitlx: The phrase "an Index* Is clarified to mean a required. Further the alternative (6) collection of documents or Indices which, when taken presented herein reflects the "as-built" together, supply the Information attributed to "an Index" condition of the Company's records storage In the standard. facilities. These facilities were constructed prior to any regulatory position being The specific location of a record "Within a storage area" defined, and, at the time of construction, (

may not be delineated (e.g., The specific location within were considered more than adequate to (

a C001)u1er record file may not be constant. Further, the assure permanent records retention. The (_

Co01)any may u1111ze a computer assisted random access discrepancies which might exist between '

filing system where such location could not be readily current guides and standards and "as-bullt"

~documented", nor would such a location be "relevant"). conditions are more than compensated for The storage location will be delineated, but where file by other more stringent measures such as, locations change within time, the specific location of a record within that file may not always be documented. a) constant surveillance of the facility both by monitoring devices, security patrqls,

2) With regard to Section 4.2 of ANSI N45.2.9 - 1974 titled and fire Inspections, and TimeUness: The Corrpany's contractural agreement with Its contractors and suppliers will constitute fulfillment of b) Permanently Installed dedicated fire the requirements of this Section. suppression apparatus.

3) With regard lo Section 5.4 of ANSI N45.2.9 - 1974 titled Preservation: The following clarification Is substituted for the current subsection 5.4.2: "Records shall be stored In enclosed containers, cabinets or other comparable document storage hardware."

17.2-81

_, June, 1986

TABLE 17.2.0 Standard, Requirement or Guide The CorTJ)any's Position Conformance Status Justification The following clarification is substituted for the current subsection 5.4.3 "Provisions shall be made for special processed records (such as radlographs, photographs, negatives, microfilm and magnetic media) to prevent damage as appropriate to the record type and will t address the manufacturer's recommendations." J

4) With regard lo Section 5.5 of ANSI N45.2.9 - 1974 litled Safekeeping: Routine general office and nuclear site security systems and access controls are provided.

5) With regard lo Section 5.6 of ANSI N45.2.9 - 1974 titled (

fadlilx: Records shall be forwarded to the appropriate (,

records storage facility promptly after completion when C

required processing and reviews have been completed.

(

)

Paragraph 4, subsection 3 Is clarified to require a two- J hour minimum fire rating to be consistent with the 1979 version of the Standard and NRG Criteria for Record Storage Facmties (Guidance - ANSI N45.2.9, Section 5.6) Issued 7/15179.

Paragraph 4, subsection 9 is clarified to read: "No pipes or penetrations except those providing fire protection, lighting, temperature/humidity control, or communications are to be located within the facility and they shall comply with a minimum two-hour fire protection rating.

.Ao2 JW,°1986

TABLE 17.2.0 Standard, Requirement or Gulde The Company's Position Conformance Status Justification

6) The Surry Power-Station facility conforms to ANSI N45.2.9

- 1974 as clarified in this Table except that it is rated at approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; doors, frames, and hardware are three-hour rated. This facility Is considered to meet the intent of ANSI N45.2.9 and provides adequate protection for records.

• The North Anna Power Station Records Vault meets the intent of Chapter 3 of NFPA No. 232-1975, subject to the following provisions:

a) The file room Is constructed with a mlnlrrum fire rating C of two (2) hours. (

C b) Heating, cooling and ventilation for the Ille room Is by means of a forced air system, with all fans, filters, and (;

)

heating and cooling elements located In an equipment room which Is external to the file room.

Ducts for this system are located on the celling of the '

Ille room and are provided with the standard door dampers with a minimum rating of two (2) hours where they penetrate the file room barrier to other areas of the building.

c) The file room Is provided with an early warning fire detection system and automatic fire suppression system. A protective signaling system is provided, with a remote alarm located at a constantly attended station.

i d) Telephone service is provided to the file room, with the wire penetration constructed and sealed in accordance with NFPA No. 232-1975.

17.2-83 June. 1986

TABLE 17.2.0 Standard, Requirement or Gulde The Conyany's Poshion Conformance Status JustHlcalion e) All records stored In the file room are stored in metal cabinets or rolling file shelves, which are arranged to provide adequate access and alsleways. Work not directly related to the storage, retrieval or auditing of records Is not allowed In the file room. Smoking, eating, and drinking Is prohibited In the file room.

f) A wall divides the file room Into two sections, with one section used as a flle room and the other section used for microfilming of records and/or supply storage. The dividing wall has a mlnlrrum fire rating of two (2) hours, Including the fire door dampers In the duct penetrating the wan. (

(

The North Anna Power Station Training Center Vauh meets the Intent of Chapter 3 of NFPA No. 232-1975, subject to C

)

the following provisions: -.

a) The file room Is constructed with a mlnlrrum fire rating of two (2) hours.

b) Heating, cooling and ventilation for the file room Is by means of a forced air system, with all fans, filters, and heating and cooling elements located in an equipment room which Is external to the file room.

Ducts for this system are located above the ceiling of the file room and are provided whh accordion dampers with a minimum rating of two (2) hours where they penetrate the file room bar,rier to other areas of the

. building.

c) The file room is provided with an early warning fire detection system and automatic fire suppression system. A protective signaling system is provided, with a remote alarm located at a constantly attended station.

84 ..

• , 1986

TABLE 17.2.0 Standard, Requirement or Guide The Corrpany's Position Conformance Status JustHication d) Telephone service Is provided to the file room, with the wire penetration constructed and sealed In accordance with NFPA No. 232-1975.

e) All records stored In the file room are stored in metal cabinets, which are arranged to provide adequate access and alsleways. Work not directly related to the storage, retrieval or auditing of records Is not allowed in the file room. Smoking, eating, and drinking Is prohibited In the file room.

The Innsbrook Technical Center's Vital Records Vault for (

nuclear records conforms to Uhe requirements of Section 5.6

(

of ANSI N45.2.9 - 1974 without exceptions.

(.

The Surry Training Center training records vault (Main (,

Building) conforms to the requirernents of section 5.6 ANSI )

J N45.2.9 - 1974 without exceptions.

The Surry Training Center training records vault (Slmul~tor Building) conlonns to the requirements of section 5.6 ANSI N45.2.9 - 1974 with the following exceptions:

a) The door is a UL-rated three-hour lire door.

b) The records storage vault Is constructed with a minimum fire rating of two (2) hours.

17.2-85 June, 1986

TABLE 17.2.0 Standard, Requirement or Guide NBC Regulatory Gujde 1.94 - "Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants* (Rev. 1, 4/76) - Endorses ANSI N45.2.5 - 1974.

The CorTJ)any's Position Conformance Status JustHlcalion The Operational Quality Assurance Program complies with ClarHlcation meets or exceeds applicable The proposed clarHication is used to this guide with the following clarification: guides and standards. translate construction oriented documents to operatlonal regulatlons.

See Generic Statement which prefaces this table.

1) With regard to Section 2.5.1 of ANSI N45.2.5 ° 1974 titled Selection: The Co"1)any co"1)11es with the requirement set forth In the first paragraph of this Section for selection of measuring and test equipment on the basis of sufficient accuracy to determine conformance to the C standard's requirements: This is accomplished without C the use of calibrated balances or volumetric buckets.

(

)

.86 "

June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde NRC Regu!atol)' Guide 1. 116 - "Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems" (Rev. 0-R, 6ll6) - Endorses ANSI N45.2:8 - 1975.

The Corrpany's Position Conformance Status JustHication The Operational Quality Assurance Program complies with Clarification meets or exceeds applicable This clarlf ication Is proposed as a this guide with the following clarification: guides and standards. construction to operations device.

See Generic Statement which prefaces this table.

(.

(,

C c.,

)

i 17.2-87 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde NBC Regulatory Guide 1,123 - "Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants" (Rev. 11 7ll7) - Endorses ANSI N 45.2.13 - 1976.

The Conpany's Position Conformance Status JustHlcatlon The Operational Quality Assurance Program complies with Clarifications meet or exceed applicable Clarifications contained herein reflect actual this guide with the following clarHicatlons: guides and standards. Company QA Program practices. Further.

these proposals assure continuity with the I.

.I

1) With regard to Section 1.3 of ANSI N45.2.13 - 1976 t_itled QA Program and other regulations or De(lnilions: With two exceptions (Procurement guides. and are considered to enhance the Document and Quality Assurance Program aforementioned program.

Requirements) definitions In this Standard which are not included In ANSI N45.2.10 will be used; all definitions which are Included In ANSI N45.2.10 will be used as clarified In the Company's commitment to Regulatory (

Gulde 1.74. The two exceptions are defined In Table (

17.2.0 under Regulatory Gulde 1.74. C

(.,

2) With regard to Section 1.2.2 of ANSI N45.2.13 - 1976 )

iitled Purchaser's Respons!bHH!es: Item c ts modified as  ;;

follows: *Evaluation of the supplier's QA program shall be conducted as determined by the QA Department based on the complexity and use of the procurement.*

3) With regard to Section 3.1 of ANSI N45.2.13 - 1976 titled Procurement Document Preparation. Review and Change Control: The phrase "the same degree of control" Is stipulated to mean *equivalent level of review and approval.* The changed document may not always be rerevlewed by the originator; however, at least an equivalent level supervisor shall review and approve any changes.

4) With regard to Section 3.4 of ANSI N45.2.13 - 1976 titled Procurement Document Control: The Company will meet the requirements of Sections 17.2.4 and 17.2.7 of the Operational QA Program In lieu of the requirements specified In this Section.

BB J* e, 1986

TABLE 17.2.0 Standard, Requirement or Gulde The Corrpany's Position Conformance Status Justffication

5) With regard to Section 5.3 of ANSI N45.2.13 - 1976 titled Pceaward Evaluation: The Corrpany will comply with an alternate paragraph which reads: "Except In unusual

. circumstances as determined and documented by station management (e.g., replacement parts are needed to preclude the development of some unsafe or undesirable condition at a nuclear facility), and except In those cases where dedication techniques that do not rely on the supplier's QA program are necessary (e.g. the sole use of special tests and Inspections to verify the quality of certain commercial grade items where the supplier has no formal QA program), a preaward (

evaluation of the Supplleir shall be performed as required (.

by the Operational QA Program.* (

6) With regard to Section 6.4 of ANSI N45.2.13 - 1976 titled (;

)

Control of Changes in Hems of Service: The phrase "the  :,

Operational QA Program* will be Inserted In Heu of *ANSI N45.2, Section 7:

7) With regard to Section 8.2 of ANSI N45.2.13 - 1976, tilled DisposiUon: The third sentence of Item b Is revised to read:

Nonconformances to the contractual procurement

• requirements or Purchaser approved documents and which consist of one or more of the following shall be submitted to the Purchaser for approval of the.

recommended disposition prior to shipment when the nonconformance could adversely affect the end use of a module or shippable component relative to safety, Interchangeability, operability, reliability, integrity, or maintainability:

1) Technical or material requirement is violated;*

17.2-89, June, 19~6

TABLE 17.2.0 Standard, Requirement or Gulde The CorlJ?any*s Position Conformance Status Justification

2) Requirement In Supplier documents, which have been approved by the Purchaser, Is violated:

3) Nonconformance cannot be corrected by continuation of the original manufacturing process or by rework; and/or

4) The Item does not conform to the orlglnal requirement even though the Item can be restored to a condition such that the capability of the Item to function Is unl"1)81red.

(

• A module Is an assembled device, Instrument, or piece of equipment Identified by serial number or other . (

Identification code, having been evaluated by Inspection C and/or test for confonnance to procurement requirements (

regarding end use. A shippable component Is a part of a )

subassembly of a device, Instrument, or a piece of equipment which Is shipped as an Individual Item and which has been evaluated by Inspection and/or test for conformance to procurement requirements regarding end use.

TABLE 17.2.0 Standard, Requirement or Gulde NRG Regulatory Guide 1.144 - "Audtting of Quality Assurance Programs for Nuclear Power Plants" (Rev. 1, 9/80) - Endorses ANSI N45.2.12 - 1977.

The Company's Position Conformance Status Justification r*

(

The Operational Quality Assurance Program complies with Clarifications meet or exceed applicable These clarifications have been proposed to this guide with the following clarifications: guides and standards. maintain program continuity with other referenced standards and guides committed

1) With regard to Section 1.4 of ANSI N45.2.12 - 1977 titled to In Table 17.2.0.

Definitions: With one exception (Program Deficiencies) the definitions In this Standard which are not Included In Further, where alternatives have been ANSI N45.2.10 will be used as clarified In the Company's proposed they reflect Company QA Program commitment to Regulatory Gulde 1.74. The one practices and are considered to enhance the excepted definition and clarified definition relevant to referenced program.

this standard are defined In Table 17.2.0 under (,

Regulatory Gulde 1.74. Not all standards, guides and regulations can (

be considered .programmatically error-free, C

2) With regard to Section 2.2 of ANSI N45.2.12 - 1977 titled therefore, operational experience utlllzlng '

(;

Personnel Oua!lllcatlons: The qualfflcallon of Colf1)any these documents and the proposed )

audit personnel will be accomplished as described to alternatives must be taken Into J meet the requirements of ANSI N45.2.23 - 1978 as consideration.

endorsed In Table 17.2.0 and Sections 17 .2.2 and 17.2.18 of the Operational QA Program.

3) With regard to Section 2.3 (and subsections 2 .3.1 through 2.3.3) of ANSI N45.2.12 - 1977 titled Training:

The training of Company audit personnel will be accomplished as described to meet the requirements of ANSI N45.2.23 - 1978 as endorsed In Table 17.2.0 and Sections 17.2.2 and 17.2.18 of the Operational QA Program.

17.2-91 June. 1986

TABLE 17.2.0 Standard, Requirement or Gulde The CoRJ?any's Position Conformance Status JustHlcatlon

4) Wrth regard to Section 2.4 of ANSI N45.2.12 - 1977 tilled Maintenance of Peoflclency: The maintenance of proficiency of the Company audit personnel will be accomplished as described to meet the requirement of ANSI N45.2.23 - 1978 as endorsed In Table 17.2.0 and Sections 17.2.2 and 17.2.18 of the Operational QA Program.

5) WHh regard to Section 3.3 of ANSI N45.2.12 - 1977 tilled EsseoUal Elements of the AudH System: The Co01>any wlll COJ11>1y with subsection 3.6.5 as It was originally (

written (subsection 3.2.5) In ANSI N45.2.12, Draft 3, (*

Revision 4: *Provisions for reporting on lhe C

eff ecllveness of lhe OUalily Assurance Program lo lhe responsible management.* For lhe auditing organization C (The Company), effectiveness Is reported as required by J the Individual nuclear facility Technical Specifications.

Other than audil reports, the Company may not directly report on the effectiveness of the quality assurance programs lo the audited organization when such organizations are outside of lhe Company.

Subsection 3.3.6 requirements are considered 10 be fuHiled by compllance with lhe organization and reporting measures outlined In lhe Operational QA Program and the Technical Specifications of the Individual nuclear facility.

Subsection 3.3. 7 requires verification of effective corrective action on a ilmely basis."

• 2*

June, 1986

TABLE 17.2.0 Standard, Requirement or Guide The Company's Position Conformance Status JustHication Timely basis is interpreted to mean within the framework or period of lime for cofTl)letion of corrective action that is accepted by the QA Organization. Each finding requires a response and a corrective action completion date; these dates are subject to revision (with the approval of the QA Department) and must be escalated to higher authority when there Is disagreement between* the audited and the auditing organization on what constitutes i1mely corrective action:

. 6) With regard to Section 3.5 of ANSI N45.2.12

• 1977 titled (

ScheduUng: Subsection 3.5.3.1 Is Interpreted to mean that the Company may procedurally review qualification

(

of a contractor's or supplier's quality assurance program prior to awarding a contract or purchase order by means C,

)

other than audit.  ::i

7) With regard to Section 4.3.1 of ANSI N45.2.12

• 1977 titled Pre-Audit Conference: The Company will comply with requirements of this Section by inserting the word

• Normally" at the beginning of the first sentence. This clarification is required because in the case of certain unannounced audits or audits of a particular operation or work activity, a pre-audit conference might interfere with the spontaneity of the operation or activity being audited. In other cases, persons who should be present at a pre-audit conference may not always be available.

Such lack of availability should not be an impediment to beginning an audit. Even in the above examples, which are not intended to be all inclusive, the material set forth in Section 4.3.1 will normally be covered during the course of the audit.

17.2-93 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde The COFTJlany's Position Conformance Status Justification

8) With regard to Section 4.3.2 of ANSI N45.2.12 - 1977 thled Audit Process:

a) Subsection 4.3.2.2 could be Interpreted to limit auditors to the review of only objective evidence; sometimes and for some program elements, no objective evidence may be available or subjective evidence may be more appropriate. The Company will comply with an ahemate sentence which reads:

• when available, objective evidence shall be examined for compliance with Quality Assurance (,

Program requirements. When subjective evidence Ci Is used (e.g., personnel Interviews, direct C

observations by the auditor), then the audit report i must Indicate how the evidence was obtained: Ci

)

b) Subsection 4.3.2.4 Is modified as follows to take Into account the fact that some nonconformances are virtually *obvious* with respect to the needed corrective action:

"When a nonconformance or quality assurance program deficiency Is Identified as a result of an audit, unless the apparent cause, extent and corrective action are readily evident, further Investigation shall be conducted by the audited organization In an effort to Identify the cause and effect and to determine the extent of the corrective action required.*.

• 94 u e, 1986

~-

TABLE 17.2.0 Standard, Requirement or Guide The Conpany's Position Conformance Status Justification c) Subsection 4.3.2.5 contains a recommendation which Is clarified with the definttlon of "acknowledged by a member of the audited organization" to mean that a

• member of the audited organization has been t informed of the findings.* Agreement or J disagreement with a finding may be expressed in the response from the audited organization.

9) With regard to Section 4.3.3 of ANSI 45.2.12 - 1977 titled Post-Audit Conference: The Company will substitute and comply with the follOwlng paragraph: "For all external (

audits, a post-audit conference shall be held with (

management of the audited organization to present audit . C findings and clarify misunderstandings; where no adverse findings exist, this conference may be waived by Ci

)

management of the audited organization: such waiver J shall be documented in the audit report.

Unless unusual operating or maintenance conditions preclude attendance by appropriate managers/supervisors, a post-audit conference shall be held with managers/supervisors for all internal audits for the same reasons as above. Again, if there are no adverse findings, management of the Internal audited organization may waive the post-audit conference: such waiver shall be documented in the audit report."

17.2-95 June, 1986

TABLE 17.2.0 Standard, Requirement or Guide The Company's Position Conformance Status JustHication

10) With regard to Section 4.4 of ANSI N45.2.12 - 1977 titled Reporting:

a) This Section requires that the audit report shall be signed by the audit team leader: this is not always the most expeditious route to take to assure that the audit report is Issued as soon as practical.

The Co111>any will co111>ly with Section 4.4 as clarified In the following opening statement: *An audit report, which shall be signed by the audit team leader, or his C supervisor In his absence, shall provide*: In cases C where the audit report is nor signed by the Audit (.

Team Leader due to his absence, one record copy of the report must be signed by the Audit Team ('

)

Leader upon his return. The report shall not require the Audit Team Leader's review/concurrence/signature If the Audit Team Leader Is no longer employed by the Company QA Department at the time the audit report Is Issued.

b) The Company will comply with subsection 4.4.3 clarified to read: "Supervisory level personnel with whom significant discussions were held during the course of pre-audit (where conducted), audit, and post-audit (where conducted) activities.

c) Subsection 4.4.6 requires audit reports to Include recommendations for corrective actions: the Company may choose not to comply with this requirement. Instead, Audit Team Leaders are required to document all adverse findings on audit finding forms.

.96" June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde The Corrpany's Position Conformance Status JustHlcatlon The procedure for processing audit findings allows the Audit Team Leader to document actions which are considered necessary to correct the finding; the Audit Team Leader may also document actions l which are considered unacceptable for correcting J the finding: the audit finding with these

• Recommendations* Is then transmitted to the audited organization. In addition, the Audit Team Leader Is required to review the response to the audit finding and determine H II Is acceptable.* Any disagreements must be escalated to higher C management for resolution. (

11) With regard to Section 4.5.1 of ANSI N45.2.12 - 1977 C titted By AudHed Organllatk>n: The Con-.,any will co"l)ly (

)

with the following clarlflcatlon of this Section: :J

• Management of the audited organization or activity shall review and Investigate all adverse findings, as necessary, (e.g., where the cause Is not already known, another organization has not already Investigated and found the cause, etc.) to determine and schedule appropriate corrective action Including action to prevent recurrence.

They shall respond, In writing, within thirty days after the date of Issuance.of the audit report.

The response shall clearly state the corrective action taken or planned to prevent recurrence and the results of the Investigation if conducted. In the event that corrective action Is not completed by the time the response Is submitted, the audited organization's response shall Include a scheduled date for completion of planned corrective action.

The audited organization shall take the appropriate action to assure that corrective action Is acco"l)llshed as scheduled.

17.2-97 June, 1986

TABLE 17.2.0 Standard, Requirement or Gulde NRG Regulatory Guide 1,146 * *Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants" (Rev. o, 8/80) -

Endorses ANSI N45.2.23

• 1978.

The Company's Position Conformance Status JustHlcatlon J.

(

The Operational Quality Assurance Program complies with ClarHlcallons and alternatives meet or The clariflcallons and alternatives reflect this guide with the following clariflcatlons and alternatives: exceed applicable guides and standards. experience gained at operational nuclear facilities and are Intended to enhance and

1) With respect to Section 1.4 of ANSI N45.2.23

• 1978 titled provide additional guidance In the areas of Defin!Uons: Definitions In this Standard which are not auditing as delineated herein.

lnch.Jded In ANSI N45.2.10 will be used; "AUDIT" which Is lnch.Jded In ANSI N45.2.1 O will be used as addressed In the Company's commitment to Regulatory Gulde 1.74.

2) With respect lo Section 2.2 of ANSI N45.2.23 - 1978 C titled auaUUcaUon ot Auditors: Subsection 2.2.1 (

references ANSI N45.2 therefore, the Company wlll C comply with an alternate subsection 2.2.1 which reads:

t

)

Orientation to provide a working knowledge and understanding of the Operational QA Program, Including the ANSI standards and Regulatory Guides Included In Table 17.2.0 of the Program, and the Company's procedures for Implementing audits and reporting results.

3) With respect to Section 2.3 of ANSI N45.2.23-1978 litled aua!HicaUoo of Lead Audttors: Subsection 2.3.3.1 references ANSI N45.2; therefore, the Company will comply with an alternate subsection 2.3.3.1 that reads:

Knowledge and understanding of the Operational QA Program, Including the ANSI Standards and Regulatory Guides Included In Table 17.2.0 of the P.rogram, particularly ANSI N45.2.12 and other nuclear-related CQdes and regulatlons, as applicable ..

4) With respect to Section 3.2 of ANSI N45.2.23 - 1978 titled Maintenance of Proficiency: The Company will comply with the requirements of this Section by defining "annual assessment" as one which takes place every 12 months or less and which uses the Initial date of

TABLE 17.2.0 Standard, Requirement or Gulde The Company's Position Conformance Status Justification certification (not the calendar year) as the starting dale for determining when such annual assessment Is due.

5) With respect to Section 4.1 of ANSI N45.2.23 - 1978 titled Organizational ResgonsibHllY: The Company wlll comply with this Section with the substitution of the following sentence In place of the last sentence in the Section.

The Manager-Quality Assurance, Supervisor-Quality or Audit Team Leader shall, prior lo commencing the audit, assign personnel who collectively have experience or training commensurate with the (

scope, co"1)1exlty, or special nature of activities lo be audited. C C

6) With respect to Section 5.3 of ANSI N45.2.23 - 1978 tltled (,

)

UpdaUcm of Lead Auditor's Records: The Company will :J substitute the following sentence for this Section:

Records for each Lead Auditor shall be maintained and updated during the period of the annual management assessment as defined In Section 3.2 (as clarified).

17.2-99 June, 1986

REVISION 23 12/94 SPS UFSAR ,.

TABLE 17.2.2 Appendix B Topical 10 CFR 50 Report Criterion Section ~ Abstract 17.2.1 Organization Defines the relationship of departments to the quality assurance effort associated with the operation of the nuclear power station.

II 17.2.2 Quality Assurance Defines the Operational Program Quality Assurance Program, its overall responsibility and provisions.

Ill 17.2.3 Design Control Defines the policy, responsi-bility and procedures for exercising design control.

IV 17.2.4 Procurement Establishes policy applic-Document Control able to plant operation and maintenance.

V 17.2.5 Instructions, Establishes guidelines for Procedures and preparing instructions, Drawings procedures and drawings.

VI 17.2.6 Document Control Establishes policy for the control of procedures and instructions.

VII 17.2'.7 Control of Purchased Establishes methods for Material, Equipment assuring that purchased and Services items conform to the speci-fied quality requirements.

VIII 17.2.8 Identification and Establishes procedures for Control of Material, the identification and Parts and Components control of material, parts and components.

IX 17.2.9 Control of Special Establishes procedures Processes which assure that special processes are controlled and accomplished by qualified personnel.

I 17.2-100

.,-.. REVISION 23 12/94 SPS UFSAR Appendix B Topical

• 10 CFR 50 Report Criterion Section ~ Abstract X 17.2.10 Inspection Establishes a program for inspection of activities affecting quality.

XI 17.2.11 Test Control Establishes policy for power stations test programs.

XII 17.2.12 Control of Measuring Establishes policy for con-and Test Equipment trol and calibration of test and measuring equipment.

XIII 17.2.13 Handling, Storage Establishes policy for this and Shipping function as related to material and equipment.

XIV 17.2.14 Inspection, Test, Makes reference to appro-and Operating Status priate administrative procedures which govern this function.

xv 17.2.15 Non-Conforming Establishes policy for Material, Parts, or reporting and controlling

• XVI 17.2.16 Components Corrective Action non-conforming materials, parts, or components.

Establishes policy for identifying, documenting, notifying, determining causes and preventing defects from recurring.

XVII 17.2.17 Quality Assurance Assures maintenance, identi-Records fication and retrievability of records.

XVIII 17.2.18 Audits Defines policy and procedures for audit programs .

• 17.2-101

REVISION 23 12/94 SPS UFSAR APPENDIXC NUCLEAR REGULATORY COMMISSION CORRESPONDENCE 17.2-102

UNh'a,'

NUCLEAR REGULATORY COMMISSION

... REGION I 101 MARIETTA. STIIEET. N.W** SUITE 2IDD ATLANTA. GEORGIA 3lm301* . Rec'd AUS 2 4 1993 August 19, 1993

• Docket Nos. 50-338, 50-339, 50-280, 50-281 License Nos~ NPF-4, NPF-7, DPR-32, DPR-37 Virginia Electric and Power Company ATTN: Hr. W. L. Stewart Nuclear Licensing Senior Vice President - Nuclear 5000 Dominion Boulevard Glen Allen, VA 23060 Gentlemen:

SUBJECT:

OPERATIONAL QUALITY ASSURANCE PROGRAM CHANGES, TOPICAL REPORT We have received your letter of July 28, 1993, requesting changes in your quality assurance.prograa requireaents. As stated in your letter, five of the changes reduce the c01111itments in the QA program previously approved by the Nuclear Regulatory Coaaission. This request is currently being reviewed. We will notify you of the results of our review at a.later date.

If you have any questions concerning this letter, please contact Mr. Frank Jape at 404-331-4178.

ii]Y,~ k_,---

• cc: H. L. Bowling, Jr., Manager Albert F. Gibson, Director Division of Reactor Safety Nuclear Licensing Virginia Electric &Power Company 5000 Doainion Boulevard Glen Allen, VA 23060 G. E. Kane, Station Managar North Anna Power Station P. o. Box 402 Mineral, VA 23117 Executive Vice President Old Doainion Electric Cooperative 4201 Dominion Boulevard Glen Allen, VA 23060 (cc cont'd - See page 2)

• 17.2-103

REVISION 23: 12/94 SPS UFSAR Virginia 'Electric and Power 2 ,to, August 19, 1993 Company (cc cont'd)

Dr. W. T. Lough Virginia Corporation Connission Division of Energy Regulation P. O. Box 1197 Richmond, VA 23209 William C. Porter, Jr.

County Administrator Louisa County P.O. Box 160 Louisa, VA 23093 Michael W. Maupin, Esq.

Hunton and Williams Riverfront Plaza, East Tower 951 E. Byrd Street Richmond, VA 23219 Attorney General Supreme Court Building 101 North 8th Street Richmond, VA 23219 Robert 8. Strobe, M.D., M.P.H.

State Health Coanissioner Office of the Coaaissioner Virginia Department of Health P.O. Box 2448 Richmond, VA 23218 H. R. Kansler Station Manager Surry Power Station P.O. Box 315 Surry, VA 23883 Ray D. Peace, Chairman Surry County Board of Supervisors P.O. Box 130 Dendron, VA 23839

• 17 .2-104

UNITED STATES NUCLEAR REGULATORY COMMISSION ;erial~-q~L}...;...-~l':l..._3_

REGION II

_.... ' 101 MARIETTA STREET, N.W., SUITE 2900 ATLANTA, GEORGIA 30323-0199 Rec'd MAR 7 199t, February 28, 1994

• Docket Nos. 50-338, 50-339, 50-280 and 50-281 License Nos. NPF-4, NPF-7, DPR-32 and DPR-37 Virginia Electric and Power Company ATIN: Mr .. W. L. Stewart Nucl~?:- Licensing Senior Vice President - Nuclear 5000 Dominion Boulevard Glen Allen, VA 23060 Gentlemen:

SUBJECT:

ACCEPTANCE OF CHANGES TO THE OPERATIONAL QUALITY ASSURANCE PROGRAM TOPICAL REPORT VEP l-5A (UPDATED) FOR SURRY UNITS 1 AND 2 AND NORTH ANNA UNITS 1 AND 2 Thank you for your letter dated July 28, 1993, (serial No. 93-406} notifying us of changes to your Operational Quality Assurance Program in accordance with IO CFR 50.54 (a){3). We have completed our review of the changes addressed in your submittal. The changes identified as a reduction in commitments do not reduce your program below 10 CFR 50, Appendix B requirements. The change related to periodic reviews of procedures provides an acceptable alternative process to ensure procedures in use are accurate and provide the best possible instructions for safety related activities .

• The alternative process and the reduction in commitments are as described in ANSI NIB.7 1976. Implementation of these changes requires an approved change to Technical Specification 6.8.2. Therefore implementation must be delayed until the Technical Specification is approved.

We have concluded from our review that the changes to your Quality Assurance Program are acceptable. The review indicates that the Operational Quality Assurance Program Topical Report VEP l-SA {Updated) continues to satisfy 10 CFR 50, Appendix 8 requirements, and is acceptable.

We appreciate your cooperation with us. Should you have any questions concerning this letter, please contact Frank Jape of my staff at 404-331-4178.

Albert F. Gibson, Director Division of Reactor Safety

{cc w/o encl: See page 2)

• 17.2-105

SPS UFSAR Virginia Electric and 2 February 28, 1994 Power Company cc w/o encl:

M. L. Bowling, Jr., Manager Nuclear licensing Virginia Electric & Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 G. E. Kane, Station Manager North Anna Power Station P.O. Box 402 Mineral, VA }3117 M. R. Kansler Station Manager Surry Power Station

. P. 0. Box 315 .

• Surry, VA 23883 Ray D. Peace, Chairman Surry County Board of Supervisors P. 0. Box 130 Dendron, VA 23839 Executive Vice President Old Dominion Electric Cooperative 4201 Dominion Boulevard Glen Allen, VA- 23060 Dr. W. T. Lough Virginia Corporation Commission Division of Energy Regulation P. 0. Box 1197 Richmond, VA 23209 William C. Porter, Jr.

County Administrator Louisa County P. 0. Box 160 Lo~isa, VA 23093 Michael W. Maupin, Esq.

Hunton and Williams Riverfront Plaza, East Tower 951 E. Byrd Street Richmond, VA 23219

{cc w/o encl cont'd - See page 3) 17.2-106

• IU:.VJ.~lUN ~J 12/94. SPS UFSAR Virginia Electric and 3 February 28, 1994 Power Company

• (cc w/o encl cont'd)

Attorney General Supreme Court Building 101 North 8th Street Richmond, VA 23219 Robert B. Strobe, M.D., M.P.H.

State Health Commissioner Office of the Commissioner Virginia Department of Health P. 0. Box 2448 Richmond, VA 23218

\..

• 17 .2-107 J