RC-98-0229, Fifteenth Annual 10CFR50.59 Rept for VC Summer Nuclear Station, for Period Ending 970806.With

Fifteenth Annual 10CFR50.59 Rept for VC Summer Nuclear Station, for Period Ending 970806.With

ML20198P299
Person / Time
Site:	Summer
Issue date:	08/06/1997
From:	Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RC-98-0229, RC-98-229, NUDOCS 9901070023
Download: ML20198P299 (20)

Text

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$W, gdy.] oGentlemen:  :

{MWf. , , pm! VIRGIL C. SUMMER NUCLEAR STATION ppp s ' , 'Q)

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[- @#.My Nigw 10 CFR 50.54(a)(3) /10 CFR 50.59(b)(2) ANNUAL REPORT f

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fo ub i N sa$ South Carolina Electnc & Gas Company (SCE&G) is subm Report pursuant to 10 CFR 50.59(b) and 10 CFR 50.54(a) for Virgil C. Summer p T%^,d}w l Nuclear Station.

i p &p<wVMyj This report contains a brief description of changes and modifications made to the k i NhM !facility, as described in the- Final Safety Analysis Report (FSAR) and the Fire ,

M Protection Evaluation Report (FPER), as well as a summary of the safety evaluations M@E : ~ , . ; Q' j h] performed to evaluate these changes N  ;

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• 9' Non-Conformance Notice [NCN] numbers), p numbers) Modification Changes (identified by the Modification Request h@ScX Md Form [MRF] and Modification Change Notice [ MON] numbers) and Engineering tiicHosM Change Requests (identified by the Engineering Change Request [ECR] numbers) 5ewh(edap%wSym?

K5mm were completed during the time frame of one year prior to August 6 '

f 0.h44L 41 % ended the fifteenth year following the issuance of the VCSNS Operating License.

There. were no reportable changes to the quality assurance program during this Wg[_ '

%]ypenod.

MM4% ',1 i3 Should you have any questions, please call Mr. Donald L. Jones at (803) 345-4480.

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i Enclosura td Docum:nt Control Desk Lett:r RR 8450 RC-98-0229 Page 1 of 19 i

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4 FIFTEENTH ANNUAL 10CFR50.59 REPORT VIRGIL C. SUMMER NUCLEAR STATION i

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RR 8450 RC 98-0229 l Page 2 of 19 i

FIFTEENTH ANNUAL 10CFR50.59 REPORT VIRGIL C. SUMMER NUCLEAR STATION t

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Acronyms and abbreviations used throughout this report are listed on the last page.

i-j Identification No.

Description:

FSAR RN 95-05 This change to the FSAR revised Section 9.3.1 to correct '

inconsistencies in design and operational information for i the Spent Fuel Cooling System. This change does not i involve any unreviewed safety questions.

! FSAR RN 95 34 This change to the FSAR identified several additional Rev.1 figures and sections to reflect the changes performed

! under MRF 21073 (previously reported in the 14th Annual

' Report). This change does not involve any unreviewed

safety questions.

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FSAR RN 95-37 This change to the FSAR revised FSAR Figures 6.2-68, 6.2-76,6.2-79, and 10.4-12 to reflect the changes performed under MRF 90003 (reported in the 13th Annual Report). These changes do not involve any unreviewed

safety questions.

E FSAR RN 95-38 This change to the FSAR revised Section 11.6 to state that the Offsite Radiological Monitoring Program is i described in the Offsite Dose Calculation Manual (ODCM) instead of referencing the Operating License Environmental Report (OLER). Technical Specification  ;

Administrative Control 6.8.8.(f) requires that an environmental monitoring program be established

consistent with Appendix l to 10CFR50 and be contained 7 in the ODCM. It is therefore appropriate that the FSAR reference the ODCM for the description of the

, - Radiological Environmental Monitoring Program. This change does not involve any unreviewed safety questions.

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" Enclosure td Docum:nt Control D si. Lattar RR 8450 RC-98-0229 Page 3 of 19 Identification No.

Description:

FSAR RN 95-40 This change to the FSAR alicwed the use of oxygen scavengers other that hydrazine. This change affected FSAR Sections 10.3.5,-10.4.8.1.3,10.4.8.1.5, and 10.4.8.1.6. This change does not involve any unreviewed safety questions.

FSAR RN 96-04 This change to the FSAR revised Figure.1.2-1 that was Rev.1 not previously included in FSAR RN 96-04 Rev. O and MRF 22337 (reported in the 13th Annual Report). This change does not involve any unreviewed safety questions.

FSAR RN 96-10 This change to the FSAR revised Figure 1.2-15,12.1-19 and 12A.4-7 to reflect changes to partition walls for an office area. This change does not involve any unreviewed safety questions.

FSAR RN 96-13 This change to the FSAR revised Figures 5.5-4 and 6.31 FSAR RN 96-58 to show compression fittings installed to facilitate drainage and LLRT. These changes do not involve any unreviewed safety questions.

FSAR RN 96-15 This change to the FSAR revised Figure 5.2-8 to reflect the change to the Residual Heat Removal System under l ETBT-404, replacing the existing drain valves with larger ones and adding isolation valves. This change does not involve any unreviewed safety questions.

FSAR RN 96-16 This change to the facility installed hardware in the MRF 22740 refueling macliine needed to support in mast fuel sipping for failed fuel detection. This change affected FSAR Sections 9.0,9.1.4.2.2.1 and 9.3.5 and Figures 9.1-14 and 9.3-43. These changes do not involve any unreviewed safety questions.

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• Enclosuro to' Document Control Desk Lcitar RR B450 RC-98-0229 Page 4 of 19 Identification No.

Description:

FSAR RN 96-19 These changes to the FSAR revised several figures as Rev.1 - 6 part of the FSAR reconciliation project and included MRFs MRF 21740 21632D,21740, 21746, MONS 21746A-D, 22362, MRF 21746 22640, and 34889. MRF 21740 added bypass and drain MCN 21746A D lines to allow draining portions of the SW System from MRF 22640 outside the RB. MRF 22640 updated documentation on various system valves. MRF 21746 and associated MCNs 21746A D installed bypass lines on HVAC chiller SW outlet piping for better cold weather control. These changes do not involve any unreviewed safety questions.

FSAR RN 96 21 This change to the FSAR revised Figures 1.2-1, 2.4-1, 2.4-6,2.1-3, and 9.5-1 as well as Sections 1,2,3,9 and 11, to reflect the changes performed under MRF 90008 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.

FSAR RN 96-22 This change to the plant installed permanent removable MRF 21628 shielding around the RHR and SI piping in various areas MCN 21628A of the plant. This change affected FSAR Figures 12.1-1, 12.1-10, and 12.1-12 and Table 3.2-2. These changes do not involve any unreviewed safety questions.

FSAR RN 96-23 This change to the FSAR r vised Figure 9.4-11 to remove MCN 22679D the High Delta-P alarm switch from the Fuel Handling Building HVAC System. This change does not involve any unreviewed safety questions.

. FSAR RN 96 24 This plant change replaced the obsolete seismic l MRF 22665 instrumentation with a solid-state instrumentation system.

This change affected FSAR Section 3.7.4, Tables 3.7-10 and 3.7-11, and Figures 3.7-49 and 3.7-50. These changes do not involve any unreviewed safety questions.

FSAR RN 96-25 This change to the FSAR revised Figure 1.2-16 and 12.1-19A to reflect the changes performed under MRF 22741 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.

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Description:

FSAR RN 96-26 This change to the FSAR affected Section 9.3.4, Table 3.9 8, and Figures 9.3-16 sheets 2,4, and 5, and 9.4-8, to reflect the changes performed under MRF 21511 (previously reported in the 12th Annual Repor1). These changes do not involve any unreviewed safety questions.

FSAR RN 96-27 This change to the FSAR affected Sections 9.4.8. This change provided a method for cooling the Reactor Vessel Cavity in the event of a loss of both Reactor Cavity Cooling Fans. This change does not involve any unreviewed safety questions.

FSAR RN 96-28 This change to the FSAR revised FSAR Figures 9.2 9b FSAR RN 96-30 and 10.4-8 to reflect the changes performed under MRF MRF 90109 22293 (previously reported in the 14th Annual Report).

MCN 90109A Additionally, MRF 90109, MCN A installed flow conditioning devices used to improve the condensate suction flow patterns. These changes do not involve any unreviewed safety questions.

FSAR RN 96-29 This change to the FSAR revised FSAR Figures 9.3-18 and 11.2-2, Sheet 2, to show manual isolation valves as normally open for the boron recycle and waste evaporator concentrate drain lines. These changes do not involve any unreviewed safety questions.

FSAR RN 96-31 This change to the FSAR revised FSAR Figures 1.2-4, 1.2-5,1.2-16,9.4-1,9.4-10 and 9.3 9 and FSAR Section 9.4 to reflect the changes performed under MRF 22009 (previously reported in the 12th Annual Report). These changes do not involve any unreviewed safety questions.

FSAR RN 96-33 This change to tne FSAR revised Sections 3.5,9.4, and Figures 1.2-16, 9.4-22 through 9.4-24 to reflect the changes performed under MRF 22114 (previously l reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.

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Description:

FSAR RN 96-34 This change to the FSAR revised Section 1.2 and Figures 1.2-1,1.2-5 through 1.2-7,1.2-12,1.2-13, aril 1.2-26. to reflect the addition of the MRF 90002 modihca; ions (previously reported in the 14th Annual Report). These changes do not involve any unreviewed safety questions.

FSAR RN 96-35 This change to the FSAR revised Figure 11.2-2, Sheet 1 to reflect the changes performed under MRF 22766 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.

FSAR RN 96 36 This change to the FSAR revises Figure 1.2-7 to reflect ECR 50015 the removal of the Polar Crane " Parked Position" from the plant drawing and FSAR figure. The removal of this

" Parked Position"was evaluated under ECR 50015. This change does not involve any unreviewed safety questions.

FSAR RN 96-37 This change to the FSAR revised Figure 10.1-2,10.1-3, and 10.2-2, and Sections 3.5 and 10.2 to reflect the changes performed under MRF 22553 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.

FSAR RN 96-38 This change to the FSAR affects Section 9.1.4.2.1 to change the reference to sampling of boron concentration as specified in the Technical Specifications from daily to once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, to agree with the Technical Specification sampling frequency. This change does not i involve any unreviewed safety questions.

l FSAR RN 96-39 This change to the plant revised the alarm logic for the l MRF 22467 " Improper Lineup" alarm on the Liquid Waste System implemented under the MRF. This change affected FSAR Figure 10.4-17. These changes do not involve any unroviewed safety questions.

Enclosure to Documsnt Control Dcsk Letter RR 8450 RC-98-0229 Page 7 of 19 Identification No.

Description:

FSAR RN 96-40 This change to the FSAR revised Figures 9.2-4,9.2-7,9.4-FPER RN 96-40 23, and 9.4-27, Sections 3.9,6.3,9.2,9.3, and 9.4, and FPER Figure E-023-007 and Sections 3.2 through 3.4, 4.2,4.4, and 4.5, to reflect the changes performed under MRF 22594 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.

FSAR RN 96-41 This change to the FSAR revised various Sections and Tables to reflect the changes performed under MRF 20051 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.

FSAR RN 96-42 This plant change increased core output power to 2900 FSAR RN 96-48 MWt. The FSAR was also revised to reflect the plant FSAR RN 96-76 changes performed under MRF 90102. The changes MCN 90102A-D affected FSAR Figures 9.2-2,9.2-4, 9.3-1,10.3-1 through ICP-240.156 10.3-4,10.4-5,10.4-7A through 10.4-12,15.4-83 through Rev.1C 90 and Section 15.4, as well as Table 15.4-19. The change to the procedure revised the programming and calibration requirements for Chessell Model 344 and 345 recorders to reflect instrument setpoint changes performed under MRF 90102, MCN D. These changes do not involve any unreviewed safety questions.

FSAR RN 96-43 This change to the FSAR revised Sections 4.1,4.2,4.3, MRF 22764 and 4.4 to reflect the changes performed under core l design MRFs 22308 (previously reported in the 12th l

Annual Report), 22593 (previously reported in the 13th

! Annual Report), and 22764. These changes do not l involve any unreviewed safety questions.

FSAR RN 96-44 This change to the FSAR revised Sections 1.2,9.3 and 10.4, Figures 1.2-1,1.2-18,1.2-20,1.2-21,1.2 28,2.4-6, 9.2 8, 9.2-9A,B, and 10.4-5 through 10.4.8, as weil as Tables 10.4-3 and 10.4-9, to reflect the changes performed under MRF 90105 (previously reported in the 14th Annual Report). These changes do not involve any unreviewed safety questions.

Enclosure to Document Control Desk Lett r RR 8450 RC-98-0229 Page 8 of 19 Idgntification NA

Description:

f FSAR RN 96-45 This change to the FSAR revised Figures 9.2-8 and 9.2-9A,B to reflect the changes performed under MRF 21655 (previously reported in the 12th Annual Report). These l changes do not involve any unreviewed safety questions.

FSAR RN 96-46 This change to the FSAR revised Figures 9.2-8 and 9.2-9A,B to reflect the changes perfoi ned under MRF 22657  ;

(previously reported in the 13th Annual Report). These  !

changes do not involve any unreviewed safety questions.

FSAR RN 96-47 This change to the FSAR revised Figure 9.2-8,9.2-9A,B

\

J MRF 22023 and Section 9.2 to reflect the changes to 1% Water

. MCN 22023A Treatment System performed under MRF 22023 and MCN 22023A. These changeo do not involve any unreviewed safety questions.

FSAR RN 96-49 This change to the plant modified the operator break areas FPER RN 96-49 of the Control Room. This change affected FGAR Figures MRF 22288 9.41,1.2-15,12.1-19,12A.4-7, and 13.5-1, and FPER Figure E-023-018. These changes do not involve any unreviewed safety questions.

FSAR RtI 96-50 This change to the FSAR revised Figures 1.2-15,12.1-19 and 12A.4-7, and Sections 1.2,12.1, and 12A.4, to reflect the changes to curbs in the Radiation Protection areas performed under MRF 21546. Thes9 changes do not' involve any unreviewed safety questions.

FSAR RN 96-51 This change to the FSAR revised Figures 8.2-2B,C and Section 8.2 to change terminology used for circuit breakers. These changes do not involve any unreviewed

, safety questions.

FSAR RN 96 52 This change to the FSAR revised Figures 1.2-1 and 2.4-6 MRF 22753 to reflect changes made to the facility for vehicle barriers performed under MRF 22753. These changes do not involve any unreviewed safety questions.

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Identification No.

Description:

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[. FSAR RN 96-53 This change to the FSAR revised Section 9.3 to reflect the f

addition of air accumulators to the Diesel Generator  !

Cooler Fire Service Supply Valves (XVG-3105A/B) i performed under MRF 20787. These changes do not

[ involve any unreviewed safety questions. ,

FSAR RN 96-57 This change to the facility increased the design  !

temperature of the portion of the EFW system piping from i I

the EFW Pumps to the Steam Generators from 95'F to . -

l 150*F. This change affected FSAR Figures 10.4-12 and -

i 10.4-16. These changes do not involve any unreviewed j safety questions.  :

i This change to the FSAR revit..d Figure 9.3 9 to reflect FSAR RN 09-59 the changes performed under MRF 20167 (previously

1. reported in the 7th Annual Report). These changes do not .

involve any unreviewed safety questions.

FSAR RN 96-60 This change to the facility replaced the Pressurizer Heater circuit breakers with fusable disconnects. This change MRF 22074

[ affected FSAR Figure 8G-4. These changes do not

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involve any unreviewed safety questions.

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FSAR RN 96-61 This change to the FSAR revised Figure 10.4-8 and j Sections 5.5 and 10.4, to reibet the changes performed i under MRF 90010 (previously reported in the 13th Annual j Report). These changes do not involve any unreviewed )

safety questions. )

i This change to the FSAR revised Figure 9.2-9 and 9.2-9B FSAR RN 96-62 j to reflect changes performed under MRF 21657 i (previously reported in the 12th Annual Report). These  ;

changes do not involve any unreviewed safety questions. l l

FSAR RN 96-63 This change to the FSAR revised Figure 9.2-5 to reflect l changes performed under MRF 20285 (previously )

reported in the 12th Annual Report). These changes do  !

not involve any unreviewed safety questions.

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Page 10 of 19-Identification No.- . D.escription:

FSAR RN 96-65 This change to the FSAR revised Section 6.2 to reflect the changes performed under MRF 90010 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.

FSAR RN 96-66 -This change to the FSAR revised Table 5.2-1 to change the ASME code year and addenda for the Pressurizer j

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Relief piping. This change does not involve any unreviewed safety questions.  ;

FSAR RN 96-67 This NCN added more specific operator actions to limit NCN 5465 ' EFW leakage to a faulted S/G following a secondary side break. This change affected FSAR Section 10.4.9.3.

These changes do not involve any unreviewed safety I questions.

i FSAR RN'96-68 This change to the FSAR updated Appendix 3A to denote h the number of steam generators inspected in the first

, inspection interval following the steam generator  !

! repiccoment project. This FSAR change was made to l

agree with the change made to Technical Specification 4.4.5.1, in support of S/G replacement. These changes do

[ not involve any unreviewed safety questions.

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! FSAR RN 96-69 This change to the facility deleted the automatic closure of ,

[ MRF 22263 the VCT purge isolation valve to prevent trips of the l on-line waste gas compressors. This change affected FSAR Figure 11.3-4 and Section 9.3.4. These changes  ;

do not involve any unreviewed safety questions. ,

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, FSAR RN 96-71 This change to the FSAR revised Section 15.3.5 to reflect  !

h the analysis basis for Technical Specification 3.11.2.6.

[ This change reduces the Waste Gas Dscay Tank curie .

limit to 131,000 Cl. These changes do not involve any i unreviewed safety questions.

. FSAR RN 96 This change to the FSAR revised Figures 15.4-71 through L. 15.4-73, Sections 6.2 and 15.4, and Tables 15.4-6 and 15.4-7, to reflect the update of the hydrogen generation t

.and control analyses. These changes do not involve any unreviewed safety questions.

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' l Enclosurs to Document Control Desk Lett:r I -98 229-Page 11 of 19 Identification No.

Description:

FSAR RN 96-79 This change to the FSAR revised Figure 9.2-24 and -

Section 9.2.7 to reflect the changes performed under MRF )

. 22769 (previously reported in the 14th Annual Report). 1 These changes do not involve any unreviewed safety questions.

' FSAR RN 97_-02 This change to the facility installed permanent AP gages in MCN 21746E each of the three Chiller Rooms for use in setting the Service Water flows through the HVAC Chillers. This

• change affected FSAR Figure 9.2-2. These changes do not involve any unreviewed safety questions.

FSAR RN 97-06 This change to the FSAR revised Section 9.2.2 to reflect  :

the changes to the CCW Booster Pump autoGtart setpoint  :

as part of the FSAR reconciliation project. This change does not involve any unreviewed safety questions.

FSAR RN 97-00 Revised the Penetration isolation Verification Procedure to STP-115.001 add provisions for draining of penetrations to meet the Rev.12A requirements of GL 96-06. This change affteted FSAR Section 6.2 and Table 6.2-53. These changes do not .

involve any unreviewed safety questions.

' FSAR RN 97-10 This change to the FSAR revised Sections 3.5,5.2,6.3, 12.2, and 12A, and Tables 3.5-2,6.3-3,6.3-7,6.3-9,12.2-4, and 12A.3-1, to reflect the changes performed under ,

MRF 20482 (previously reported in the 5th Annual Report). These changes do not involve any unreviewed  :

safety questions.

FSAR RN 97-11 This change to the FSAR revised Figure 9.2-9B and Section 9.2-3 to properly label root, drain, and vent valves in the Domineralized Water System. These changes do not involve any unreviewed safety questions.

FSAR RN 97-17 This change replaced failed level probes in the Leak  ;

~ MRF 34428 Detection System with newer, more reliable switches. NCN DNCN 5304 5304 provided the justification for temporarily accepting c the failed level probes until replacement under the MRF.

This change affected FSAR Sections 6.3 and 7.6. These changes do not involve any unreviewed safety questions.

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Page 12 of 19 E Identification No. Qescription: -

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FSAR RN 97 This change to the FSAR revised Table 3.9-8 and Section l 3.9 to reflect the changes performed under MRF 90003 1 (previously reported in the 13th Annual Report). These j changes do not involve any unreviewed safety questions. -

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. FSAR RN 97-21 This change to the FSAR separates the procedure for i lifting the reactor vessel head from the procedure for filling j the refueling cavity, and provides for filling the cavity via '

9 the spent fuel cooling pumps. This change affected Section 9.1.4. These changes do not involve any unreviewed safety questions.

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i . FSAR RN 97-23 This change to the facility replaces the main telephone

!, ECR 50043 switches. This change affected FSAR Section 9.5.2. t i These changes do not involve any unreviewed safety questions.

FSAR RN 97-28 This change to the FSAR revised Section 10.4 and Table 10.2-0 to reflect the changes performed under MRF 20726 i (previously reported in the 7th Annual Report). These l I

changes do not involve any unreviewed safety questions.

FSAR RN 97-29 ~ This change to the FSAR revised Section 6.2.2 to update the incore instrumentation pit volume for use in the RB flooding analysis. This change does not involve any unreviewed safety questions.

FSAR RN 97-35 This change to the facility upgrades the chemistry MRF 22024 sampling instrumeitts in the Water Treatment Plant. This ,

change affected FSAR Figure 9.2-9 and Section 9.2.3.

These changes do not involve any unreviewed safety questions.

FSAR RN 97-39 This change to the FSAR revised Sections 1.2.3 and 9.2.1 i to reflect the changes performed under MRF 10759 )

(previously reported in the 4th Annual Report). These j changes do not involve any unreviewed safety questions.

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!. Page'13 of 19-g identification No. Descript,igrn FPER RN 97-12 This plant change installed Appendix R fire switches on MON 22594Q XPP-0001B and XPP-00010 in the CCW System. The FEP-1.0 Fire Emergency Procedure and the Fire Switch Lineup

!' Rev.90 Verification Prm:edure were revised to reflect these new STP-170.004 fire switches. This change also affected FPER Section Rev.1C 4.5. These chariges do not involve any unreviewed safety F questions.

b MCN 20951E This change to the facility installed portions of the new fire  ;

protection and contron system in the Nuclear Operations

! Building, the Warehouses, the Craft Training Building, the Radweste Laundry Room, the Compactor area, the '

Mechanical Maintenance Suilding, the Turbine Generator Exciter Housing and the Circulatin0 Water intake Structure. This MON installed new local control panels, conduit and cable, manual alarm stations and audible appliances, and pressure switches. These changes do i not involve any unreviewed safety questions. 1

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MRF 2:1726 This change to the facility installed a post indicator valve )

in the fire service loop to allow instal!ation of a sprinkler I system to a site support office building. This change i affected FSAR Figure 9.5-1, Sheets 1 through 5, and Section 9.5. These changes do not invo!ve any unreviewed safety questions.

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MRF 22767 This change to the facility installed new conduit and MON 22767A,8 cables to support the installation of the Emergency information System. This change affected FSAR Figures 1.2-16 and 12.1-19A. These changes do not involve any unreviewed safety questions.

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' Page 14 of 19 Identification No.

Description:

MRF 34911 NCNs 4894 and 4911 earlier identified discrepancies NCN 4911 = between the hydraulic calculations and actual field NCN 4894 conditioris for the Control Building Preaction Fire Suppression System, and conditions where the hydraulic '

demand exceeded the available capacity. These NCNs provided technical justification for allowing the system to remain as is until long term design changes could be made. MRF 39411 provided a complete reanalysis of the s' Preaction Fire Suppression System and specified modifications to the system to provide for more efficient use of the flow capacity available to the system. These

!~ changes do not involve any unreviewed safety questions.

j: ECR 50002 This change to the facility installed new fiber optic ,

i communications equipment to replace microwave >

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- equipment which was removed. This change affected

! FSAR Figure 1.2-16 and Section 9.5.2. These changes

do not involve any unreviewed safety questions. .

ECR 50019 This change to the facility removed the PAP electrical and g support equipment prior to demc!ition of the PAP. This

change affected FSAR Figure 2.4-6. These changes do not involve any unreviewed safety questions.

ECR 50028 S - This change replaced the existing Industrial Cooling Water i System Cooling Towers with more efficient models. The scope of the modification included changes to the j Industrial Cooling Water System piping, changes to the j tower support structures, and evaluations of the

< implementation of the project while the p unt was at power operation. These changes do not involve any unreviewed i safety questions.

i ECR 50044 This change installed several security delay fences with personnel and vehicle access gates to enhance the

VCSNS Security Department's defense of the plant.

i_ These changes resulted from preparaCcas for the

Operational Safeguards Response EVAation (OSRE).

. These changes do not involve any unreviewed safety l questions.

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RC-98-0229

Page 15 of 19 l l

! Identification No.

Description:

i ECR 50045 This change installed several anti-ballistic shields 1 L throughout the plant to enhance the VCSNS Security ,

. Department's defense of the plant. These changes 1

resulted from preparations for the OSRE. These changes

do not invcive any unreviewed safety questions.

, i l ECR 50046' This change installed several security door delay devices l to enhance the VCSNS Security Department's defense of i

the plant. These changes resulted from preparations for l the OSRE. These changes do not involve any unreviewed safety questions.

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! ECR 50047 This ECR removed three doors from the plant in order to l . enhance the VCSNS Security Department's defense of the plant. These changes resulted from preparations for the  ;

OSRE. The ECR evaluated the removal of the doors and ,

provided details for closure of the doorway openings with  !

j reinforced concrete and concrete masonry. This change i

does not involve any unreviewed safety questions.

ECR 50054 This plant modification changed the high concentration alarm setpoints for Waste Gas Recombiner H2 and O2  ;

inlet analyzers to alarm to meet Technical Specification ,

requirements. These changes do not involve any unreviewed safety questions.  ;

ECR 50059 This change to the facility added he Leading Edge Flow Meter temperature and flow devices on the Main Feed Water System. This change affected FSAR Figure 10.4-11. These changes do not involve any unreviewed safety questions.

Railspur Removal This change removed several sections of railspur track PO N667149 which had not been used in many years and had become  :

e unnecessary. The rail material was removed for salvage purposes. This change affected FSAR Figures 1.2-1 and 2.4-6. This change does not involve any unreviewed safety questions.

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' Page 16 of 19 i . Identification No.

Description:

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j. ' NCN 96-0301 L This NCN accepted a potential condition of the Alternate FEP-4.0 High Head SI Cold Leg Recirculation Valve spuriously

Rev. 2C - opening during a fire vue to a hot short. The Fire

Emergency Respons.s Procedure was revised to provide

, compensatory action. These changes do not involve any '

unreviewed safety questions.

l EPP-100 The Radiation Emergency Plan was revised to reflect that Rev 38 the Emergency Offsite Facility would be activated at a Site

!- Area Emergency or higher classification. This change to i _ the Radiation Emergency Plan does not decrease the

effectiveness of the plan.

i EPP-100 The Radiation Emergency Plan clarified existing Rev. 39 commitments with editorial changes and reflected the deletion of the ERONS System for emergency response notification. This change to the Radiation Emergency Plan ,

does not decrease the effectiveness of the plan.

ES-560,120 Revised the procedure for Feedwater flow rate and l

! , Rev.1 temperature normalization surveillance to change the

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methods for adjustment of temperature normalization constants and presents a new adjustment for a constant

~ for normalizing Feedwater flow rate. These changes do j not involve any unreviewed safety questions. j i FEP-4.0 Revised the procedure for Control Room evacuation due i Rev. 2B to a fire to refer to starting the CCW Pump using the local Appendix R Stop/ Start switch. This change does not j involve any unreviewed safety questions.

HPP 626 Deleted the procedure for the calibration and use of the Rev. 2B Eberline HFM 6 (hand and foot monitor) because this type monitor has become obsolete. This change does not

. involve any unreviewed safety questions. l PSP-100. - This revision to the Physical Security Plan clarified Amendment 59 existing commitments and specified access control options in support of the PAP demolition. This changa to the Physical Security Plan does'not decrease the safeguards effectiveness of the plan.  !

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i identification No.

Description:

PSP-100 ~ This revision to the Physical Security Plan clarified Amendment 40 existing commitments and reflected changes implemented i' - in support of the OSRE modifications and the Vehicle

' Barrier System installation. This change to the Physical  :

Securi'.y Plan does not decrease the safeguards effectiveness of the plan. ,

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! PSP-100 This revision to the Physical Security Plan clarified {

Amendment 41 existing commitments and reflected organizational i: changes and changes implemented in support of the PAP '

. demolition. This change to the Physical Security Plan does not decrease the safeguards effectiveness of the

plan.

! PTP-125.013 This procedure was newly developed to test the feasibility Rev.O of reducing the Turbine Building Closed Cycle Cooling l j operating pressure to the Main Turbine Lube Oil Cooler, l t ,

the Main Generator H2 Cooler, and the Generator Breaker )

i Cooling Skid. This test does not involve any unreviewed safety questions.

f PTP-125.C'4 This procedure was newly developed to test the 2A and

. Rev.0 2B Feedwater Heater vent orifices to determine if i additional venting would increase thermal performance.

This test does not involve any unreviewed safety l questions. l PTP-225.002 This procedure was newly developed to provide ,

l Rev.O instructions to test the Diesel Generator Air Start After-Coolers with cooling water isolated. This test does not involve any unreviewed safety questions.

SOP-114 Revised the Reactor Building Ventilation System Rev.15C Operating Procedure to add actions for the loss of all Reactor Cavity Cooling Fans. This change does not involve any unreviewed safety questions.

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_'i dentification No.

Description:

SOP-123 Revised the Spent Fuel Cooling System Operating F

' Rev. 9H. Procedure to change the required position of the fuel transfer tube valve to meet the requirements of GL 96-06.

. This change does not involve any unreviewed safety questions.

- SOP-409 Provided operating procedures for the Loose Parts Rev. 4 Monitoring System. This change does not involve any '

'ARP-001-XCP-615 unreviewed safety questions.

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/ Enclosura tb Docum:nt Control D=k Lett:r RR 8450 l RC-98-0229 Page 19 cf 19 ABBREVIATIONS and ACRONYMS ARP Annunciator Response Procedure ASME' American Society of Mechanical Engineers CCW Component Cooling Water i

ECR Engineering Change Request EFW Emergency Feedwater ES Engineering Services Procedure ETBT Equal To or Better Than Evaluation FEP Fire Emergency Procedure 4

FPER Fire Protection Evaluation Report FSAR Final Safety Analysis Report GL Generic Letter HPP Health Physics Procedure HVAC Heating, Ventilation, and Air Conditioning '

MCN Modification Change Notice MRF Modification Request Form MWt Megawatts (thermal)

NCN Non-Conformance Notice ODCM Offsite Dose Calculation Manual 0LER Operating Ucense Environmental Report i OSRE Operational Safeguards Response Evaluation PAP Primary Access Portal PO Purchase Order PSP Physican Security Plan PTP Performance Test Procedure RB Reactor Building REP Radiation Emergency Plan RHR Residual Heat Removal RN Revision Notice S/G Steam Generator SI Safety injection SOP System Operating Procedure Y STP Surveillance Test Procedure SW Service Water VCT Volume Control Tank VCSNS Virgil C. Summer Nuclear Station l

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