ML18149A158

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Summary of 860205 Meeting W/Util & Bechtel in Bethesda,Md Re Overviews & Background Info of Schedule a & B Items & Projects,Nuclear Operation Depts 5-yr Plan & Concerns on Potential IE Citation.Util Handouts Encl
ML18149A158
Person / Time
Site: Surry, North Anna, 05000000
Issue date: 05/16/1986
From: Chan T
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8605210628
Download: ML18149A158 (18)
v • d • e


Text

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Docket Nos. 50-280/281/338/339 DISTRIBUTION Docket File NRC PDR Local PDR PAD#2 Rdq APPLICANT:

FACILITY:

SUBJECT:

Virginia Electric and Power Company

)

Surry Power Stafion, Units 1 and 2 and North Arina Power Station Units 1

,J. Partlow L. Rubenstein T. Chan and 2 A. Wang MEETING

SUMMARY

REGARDING FEBRUARY 5, 1986 INTEGRATED IMPLEMENTATION SCHEDULE MEETING C. Patel OELD E. Jordan B. Grimes ACRS (10)

L. Engle C. Grimes K. Eccleston A meeting was held in Bethesda, Maryland with Virginia Electric and Power Company and NRR representatives on February 5, 1986 to discuss the Integrated Implementation Schedule (ITS) proposed amendment.

A list of meeting attendees is provided in Enclosure 1.

Items of discussion included overviews of Schedule A and B Items, background information supporting Schedule A and B projects, Nuclear Operations Departments (NOD) five year plan, the three year plan for implementing the Schedule, and concerns regarding potential IE citation resulting from IE activities.

A copy of the VEPCO presentation handouts is provided in Enclosure 2.

Enclosures:

As stated cc:

See next page

&tJ)f7 PM:PAD#3 TChan:bl 5//y/86

PAD#2 SR(J.benstein

~5/ l~/86 "8605210628 860515 PDR ADOCK 05000280 P

PDR

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Terence L. Chan, Project Manager PWR Project Directorate #3 Division of PWR Licensing-A Office of Nuclear Reactor Regulation

e Mr. W. L. Stewart Virginia Electric and Power Company CC:

I Mr. Michael W. Maupin~,

Hunton and Williams Post Office Box 1535 Richmond, Virginia 23213 Mr. Robert F. Saunders, Manager Surry Power Station Post Office Box 315 Surry, Virginia 23883 Resident Inspector Surry Power Station U.S. Nuclear Regulatory Commission Post Office Box 166, Route 1 Surry, Virginia 23883 Mr. Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 W. T. Lough Virginia Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23209 Mr. J. T. Rhodes Senior Vice President - Power Virginia Electric and Power Company Post Office Box 26666 Richmond, Virginia 23261 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30323 James B. Kenley, M.D.., Commissioner Department of Health 109 Governor Street Richmond, Virginia 23219 e

Surry Power Station Attorney General Supreme Court Building 101 North 8th Street Richmond, Virginia 23219 ATTENDANCE LIST VEPCO INTEGRATED IMPLEMENTATION SCHEDULE MEETING FEBRUARY 5, 1986 NRC-NRR T. Chan L. Engle C. Grimes A. Wang K. Eccleston VEPCO D. Fortin R. Cross N. Clark D. VandeWalle BECHTEL C. Pindzia

ENCLOSURE 2 NRC IIS MEETING AGENDA

-BRIEFLY REVIEW VA. POWER PROPOSED LICENSE AMENDMENTS

-DISCUSS NRC COMMENTS/CONCERNS WITH VA.

POWER'S SUBMITTAL

-DISCUSS EXAMPLES OF BACKUP INFORMATION SUPPORTING SCHEDULE A & B PROJECTS

-PROVIDE OVERVIEW OF SCHEDULE A AND B

-DISCUSS PROPOSED REVIEW SCHEDULE 77-RWC-2308C RESPONSIBLE INDIVIDUAL R. W. CROSS T. CHAN/L, ENGLE R. W. CROSS R. W. CROSS R. W. CROSS

,* ~

4.

I.

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Secondary w~~r Chemistry Monitoring Program The licensee *hall implement a aecondary water chemistry monitoring program to inhibit ateam generator tube degradation.

This program ahall include:

1. Identification of a aampling schedule for the critical parameters and control points for these parameter*:
2. Identification of the procedure* uaed to quantify parameters that are critical to control point*:
3. Identification of process aampling points;
4. Procedure for the recording and management of data;
5. Procedures defining corrective actions for off control point chemiatry conditions; and
6. A procedure for identifying the authority responsib~e for the interpretation of the
data, and the aequence and timing of administrative events required to initiate corrective action.

J. The lice~aee shall fully implement and maintain in effect all provisions of the Commission-approved Nuclear Security Personnel Training and Qualifications Program, including amendment* and changes made pursuant to l_O CFR 50.S4(p).

The approved Nuclear Security Peraonnel Training and Qualification* Program consists of a document withheld from public diacloaure purauant to 10 CFR 2.790(d) identified a* Surry Power Station Nuclear Security Personnel Training and Qualifications Program" dated September 15, 1980.

The Nuclear Security Personnel Training and Qualifications Program ahall be fully implemented in accordance with 10 CFR 73.S5(b)(4), within 60 days of this approval by the Commission.

All security personnel ahall be qualified within two years of this approval.

The Integrated Implementation Schedule Plan for Surry Power Station Units 1 and 2 (the Plan) aubmitted on December lJ 1985, is approved.

a) The Plan shall be followed by the licensee from and after the effective date of thia amendment.

b) The provision* of this paragraph ahall be effective for a period of three year, following the date of i1auance by the NR.C and may be renewed upon application by the licenaee.

S.

Thia license 1* effective as of the date of i*suance, and ahall expire at midnight June 25, 2008.

Enclosure Appendix A -

Technical Specification, Date of I*1uance: May 25, 1972 Surry - Unit 1 FOR THE ATOMIC ENERGY COMMISSION Original aigned by A. Giambua*o A. Giambuas~. Deputy Director for Reactor Projects Directorate of Licensing

IMPLEMENTATION SCHEDULES

  • TWO

SUMMARY

SCHEDULES

- SCHEDULE A - ITEMS WHICH HAVE IMPLEMENTATION DATE MANDATED BY NRC REGULATIONS, ORDERS OR LICENSE CONDITIONS.

- SCHEDULE B l,

REGULATORY ITEMS IDENTIFIED BY NRC RESULTING IN, A)

PLANT MODIFICATION, B)

PROCEDURE REVISIONS OR C) CHANGES TO FACILITY STAFFING REQUIREMENTS AND WHICH HAVE AN IMPLE-MENTATION DATE COMMITTED TO BY THE UTILITY.

2, ITEMS PERCEIVED BY THE UTILITY AS PROSPECTIVE NRC REQUIRE-MENTS, AND

3.

ALL MAJOR UTILITY TASKS RESULTING FROM OTHER AGENCIES AND UTILITY INITIATED PROJECTS TO ENHANCE STATION RELIABILITY OR EFFICIENCY.

RWC/LGT/2005P-l

MODIFICATIONS TO SCHEDULE A -

WILL CONTINUE TO BE THROUGH EXEMPTION OR ORDER DATE EXTENSION PROCESS UTILITY TO ATTEMPT TO ALTER SCHEDULE B WORK BEFORE SCHEDULE A MODIFICATIONS TO SCHEDULE B -

UTILITY TO PROVIDE NRC WITH PRIOR WRITTEN NOTIFICATION OF CHANGES TO COMPLETION DATES CAT LEAST 30 DAYS) TO ENABLE' FURTHER EXPLANATION OR DISCUSSION WITH NRC CAT LEAST 15 DAYS AFTER RECEIPT OF UTILITY NOTIFICATION.)

CHANGES DO NOT REQUIRE A LICENSE AMENDMENT NRC ORIGINATED CHANGES <SCHEDULE A)

NRC TO PROVIDE UTILITY A REASONABLE OPPORTUNITY TO PROPOSE OVERALL CHANGES TO OVERALL SCHEDULE, UTILITY TO INFORM NRC OF RESULTING CHANGES IN SCHEDULES.

REPORTING SEMI-ANNUAL REPORTS OF PROGRESS TO NRC ARE REQUIRED.

IDENTIFY CHANGES SINCE THE LAST REPORT.

SUMMARIZE REASONS FOR SCHEDULE CHANGES ASSOCIATED WITH REGULATORY REQUIREMENTS.

BACKUP-INFORMATION

NOD 5 YEAR PLAN
  • FOLLOWING SECTIONS ARE INCLUDED FOR BOTH STATIONS 1.0 SCHEDULE ANALYSIS 2.0 PROJECTS

SUMMARY

3.0 COST

SUMMARY

4.0 RESOURCE REQUIREMENTS 5.0 COMMITMENTS 6.0 OUTAGES 7.0 POTENTIAL PROJECTS 8.0 PROJECT DESCRIPTIONS 77-RWC-2148B e

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Lo,,/\\ t I vN P~OJtcr MANAGEMfNT PAGE 1 OF t SHEET 4 OF 10 lNFOMMATION ~fSTEU

~:ttdeQL S ACTl\\'I TY ACTIVITY ACTIVt ry 1911~

1986 19117 IH8 1989.

NAME DESCRIPTION CODE 0001 UNIT 1 REFUELING 19115 001 0

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0,,,12 UNTT 1 REFUELING 19117 001 0

E:::a 0003 UNIT 1 REFUELING 19811 001 0

9 0004 UNIT 2 RErUELJNG 1986 001 0

Ea 0005 UNIT 2 REFUELING 1911'1 001 0

E:3 0006 UN1f 2 REFUELING 1989 001 0

Ea 4902Y SG MANWAY t.lODS U1 OUTAGE CONSTR 081 3 oc 421 A

-**o-4902Z SG MANWAY MMODS U2 OUTAGE CONSTR 081 3 oc a

446 4903 121 4903T DEMIN SUt,IP PMP MODS T3 ENGR 196 3 NE 112 490JV DEMIN SUt.lP Pt.IP IAODS CONSTR 196 3 NC

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4904 1~

4904N CONTAINMENT PERSONNEL AIR SUPPLY lAODS NE 4905 14 4905T t.lACHJNE SHOP MODS T3 ENCR 196 3 NE 4905V t.lACHINE SHOP MODS CONSTR 196 J NC

~ 29 4907 85 4907T AUX FW OIL AL ARIA TJ ENGR 090 J NE 7

4907V AUX FW OIL ALARIA CONSTR 090 3 NC I ~

4911 491 lT DIESEL ROOM DOOR IAODS (CANCELLED) 196 3 NE I-4914 115 75 78 59 4914V TRAINING EQPT 166 S NC 4980 4980S TG THERt.lAL DETECTION T2 ENGR 093 2 NE -

220 4980T TG THERMAL DETEC 0TION Tl ENGR 093 J NE 4980U TG THERMAL DETE<;TION r.tATL DELIVERY 093 3 NC 1061 4980Y TG THERMAL DETECTION U1 OUTAGE CONSTR 093 3* 0(;

CJ 4985 62 4985T NITROGEN HDR VALVE TJ ENGR 087 3 NE 52 1~3.

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4985U NITROGEN HDR VALVE MATL DELIVERY 087 J NC 4985V NITROGEN HOR VAL VE U1 OUTAGE CONSTR 087 J oc a

  • 4985Z NITROGEN HOR VAL VE U2 OUTAGE CONSTR 087 J oc a

4987 87 7

4987T TURB BLDG ROOF IAODS TJ ENGR 084AJ NE 4987V TURB B(DG ROOF MODS CONSTR 0&4A3 NC C

4995 241 4995\\/

SECONDARY PP.ESSURE UPGRADE 093 3 NC 154 S600 83 S600T NON-REGEN HX DhAIM MODS TJ ENCR 1 :l3 J NE 5600V NON-REGEN HX DRAJN MOD~ Ul OUTAGE corisTP.

123 J oc a

A 5600Z NON-REGEN HX DRAIN MODS U2 OUTAGE CONSTR 123 J oc a

560J 240 S60JS SECURITY ENTRANCr. \\1t£ST T2 ENGR 169 2. NF.

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JR DESCRIPTION

. CtltltIT RESPON9!

COtlftffl!NT DESCRIPTION PAG!

1 SCIURC! DOC/

CMfITHEHT ND CCltl'llffl!NT HANA.GERI' SUPERVISCII

  • .***DAT!

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f R!8 CUID! 1.1t7 II

.~;*j-'-:ltS********.:,....,..... """***.-.. *.... *,,,.....

101'311'19 NDRlH ANNA DAN INSPECTION lH>EII R8 1.127 R!*

QUIREHENTS.

DAVIS/CROSS...,.,.... **1U1!1'85. PROVIDE INTEIIIIATED LIVDC.SCHEDUL! T.S. SUMITTAL TO THE NRC FOR NORlH AmA.

850031-001 850050-001 IJ,.

11 * :: : **, ** ~ : IL 8~11. TIii ACTION IT!lt9 CALD!RIUS!HOIH!....

  • OUll/86 C!NEIIIC L TR 85-U
  • PROYID! RESPON!! CONC!RNDC

. THI ACTION ITEt1S ON RCPS TO THE NRC FOR NA.

850063-001 II 17 11 I,m REG VOL IO

  • '.'..,.,.. CALD!R/BERRYIWf 011'Hl'86 PROVIDE SUPPORT TO STATIONS AS REQ'D DI' REVI!N OF PINAL RULE FED REG ITEH 50.6161 OP VOL. SO.

850056-001 11..*..,...........

.... ;..,.),**.,.. ;...

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I,m RH VOL II CALD!R/8ERll1'WI Ml'H/86 PROVIDE SUPPORT AS REQUIRED IN 1HE REVIEW DI' FINAL 850056-002 RULE FED REG ITEH 50.6163 OF VOL. SO FOR NA.

,~~~::*~~& ~~:~:.~~.:;:;:--***,....,;,..... ~~~~.:*.,... **11n2115* NDR1H ANNA IUEG*on1 -*PROVIDE ADDmONAL INFORHA esoost-001 n

TION TO TH! NRC DH ITEtt n.0.1.

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  • 4171.' RR IUID! l, '7 II II
  • 4870 RH CUID! 1.'7 n

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4870 Rt:8 CUID! 1.'7

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J1 JI 21 ;.c*:4171.

  • HI IUID!.:1.97.**:

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  • 1 4170 tlJREG 0737 4170 RE8 CUID! 1.'7

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  • REG CUID! 1 ~ 97 ***

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4870 R!9 IUIDE 1.'7 5,-

'870 RE9 CUID! 1.97 Ill HTTUR/IICK!RCH!R... *u/191'81 NA 1* 1.a. 1.97-INSTALL CIUALIP'D CLOSED/NOT CLOSED 8S0052-001

. POSITIDH JMJICATIDH FOR SPECIFIED VALVESCITEH 2. )

G!TTl.!Rltl:lt!RCHER 1!/19/85 Hll R.C. 1.97-HOOIFY Hiett PRESSURE SAFETY INJEC-850052-002 TION FLOW TRANSNITIERS & NOTIFY TH! NRC lITEH 10>.

  • '............. ~...-:.. ;. **. *........... '*~*** ******.........

l!TTL!RlttOt!RCHER 1U1t/85 NAl R.G. 1.97-ttooIFY SW NATER TEl1P INSTRU.CH~LS 850052-oo,

& NOTIFY 1HE NRC lITEH l~) VA PWR LTR 85-094.

.. G!TTI.ERlttOtERCHER

t!/19181'.NAl"lt.G. 1.97-INSTAll. NEN"CAT *t now INSTRU CHAN-850052-005 NEL IN SW RETURN HEADER & NOTIFY 1HE NRClITEH 15).

  • lfTTURltlCK!RCH!R.
  • 1ui 9/81. NAl 11.1. 1. 97-ttOOIPY !ttERG DANPER POSinDH It1JICA* 850052-006 TIDH & INSTALL EQ'D lIHIT SNITCHES lITEH 161.

G!TTLERl'SAIHJERS 1!/191'8! NDR111 A...-. 1 l<<JREG 07]7 AccousncAl t1JHITORING

.SYSTEH FUHCTIONAL.ltlJ NOTIFY THE NRC.

850016-001 G!TTL!RltlCK!RCHEII 1U19l'8S NDR11f ANNA 1 REG CUID! 1.97 * :tttPLHENT REQUIREHENT 850013-001 EXCEPT FOR INCORE TC INSTALLAnotWIJ NOTIFY NRC.

  • cETTLERIHCltERCHEII.

05102/86

  • talH ANNA! REG CUIDE 1.97 - IttPltHENT EXCEPT FOR 850013-00!

INCOR! TC INSTALLATIDH & NDnFY NRC.

ll!TTI.ER/SAUtlJERS.. OI/OU86. NDRlH ANNA 2 tlJREG 0737

  • ACCOUSTICAL tlJHITORING

... SYSTEH FUNCTIONAL AND NOTIFY THE NRC.

850016-0ot.

CETTLER/HCKERCHER OS/021'86 NA2 R.C. 1.97-INSTAll QUALIFIED CLOSED/NOT CLOS-850052-007

.. ED POSinDH IHIJICATIDH FOR SPECIFIED VALVESlITEH21 GETIL!RIHCKERCHER 05/021'86 NA! R.G.1.97-HODIFY HICH PRES9 SAFETY INJEC FLOW 850052-008 Xt1TR9 & CAT l EQ'D INSTRUMENT CHANNELS CITEH 10).

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SURRY 2 1986 REFUELING OUTAGE

SUMMARY

I. Outage Schedule 10-17~86 through 12-14-86 II. Planned duration 58 days III. ~jor Work Activities A.

Refue 1 fng Estimated Duration-Days 27 B.

Construction Projects

1.

IR 4925 Reg. Guide 1.97

2.

IR 4991 Appendix "R" Modifications

3.

IR 5308 Feedwater Heater Replacement

4.

IR 5337 AC Vital Bus Upgrade

5.

IR 5351 Replace Service Water Valves

6.

IR 5358 SI Leakage Monitor

7.

IR 5359 Containment Sump Drain Trip Valves

8.

IR 5413 RCP Thennal Barriers

9.

IR 6158 NUREG 0696 SPDS C. 0 & M Projects

1. Steam Generator
a.

EC Inspection

b. Tube Plug/Leak Repair
2. Turbine Work
3. Major Equipment Overhaul
a.

RCP Seals

b. Grinnel Valves
c. Service Water Valves and RSHXs
4. Testing
a. Type C
b.

SY and RV

c. Station Breakers
d. Type A S.

PMS MOY N48 N30 48 48 26 38 38

~30

') 30 12 10 42 32 26 38 38 29 22 8

30 IV.

Work Activities With High Dose Exposure A. Refueling Estimated Dose Man-rem (~o shielding) 14(0PS) Bb(Other) 77-RCB-20488-3

e Unit 2 (Cont'd)

B. Construction Projects

l. IR 4925 Reg Guide 1.97 2..

IR 5358 sr Leakage Monitor

3.

IR 53~9 Containment Sump Drain Trip Valves

4.

IR 5413 RCP Thenna1 Barriers C. 0 & M Projects

1. Steam Generator
2.

RCP V. Major Licerising CofflTlitments IR 6158 Safety Parameter Display System IR 4925 Reg. Guide 1.97 IR 4991 IR 5413 IR 5409 Appendix R Modifications RCP Thermal Barriers ATWS Modifications

  • No estimate available at this time.

77-RCB-20488-4

> 50 77 15 --~.

IO/Generator 20/Pump

IRI 4925 4991 5308 5337 5351 5358 5359 5413 6158 PRELIMINARY LIST OF OUTAGE RELATED CAPITAL PROJECTS WITH CONSTRUCTION SCHEDULED DURING 1986 SURRY UNIT 2 REFUELl!G OUTAGE 10-17-86 THROUGH 12-14-86 ESTIMATED CONSTRUCTION REGULATORY AMOUNT OF OUTAGE DESCRIPTION COM't1ITMENT NON-OUTAGE WORK DURATION.

Reg. Guide le97 NRC Minor 48 Days(9067 M~D)

Appendix *R* Modifications NRC Significant 30 Days(l460 M-D)

Feedwater Heater-Replacement I

None Minor 48 Days(3609 M-D)

AC Vital Bus Upgrade 3

None Minor 30 Days(1424 M-D)

Service water Motor Operated Butterfly Valve None None 26 Days(284 M-D)

SI Leakage Monitor None Minor 38 Days(276 M-D)

Containment Sump Drain Trip Valves None None 38 Days(114 M-D)

Install RCP Thennal Barriers NRC None 30 Days NUREG 0696 SPDS NRC Significant 30 Days NOTES:

1.

Outage date based on 3 year forecast, dated leot. 4.19RS

2.

Scope of Work is such that all 12 feedwater heaters and drain coolers cannot be replaced during a 58 day outage. Project completion will be scheduled for.the 1988 and 1989 refueling outages.

3.

It 1s planned to accomplish this project over the 1986 and 1988 refueling outages.

77-Pn-?nlnR-7 ESTIMATED CONSTRUCTION MAN-REM iNO SHIELDING) 50 N/A N/9 N/A 17 15 N/A e

e OVERVIEW OF SCHEDULE A AND B SCHEDULE A

  • SURRY - 5 ITEMS R.G. 1.97 NUREG 0700 - CONTROL ROOM DESIGN REVIEW (CRDR)

APPENDIX R ATWS NUREG 0696 - SAFETY PARAMETER DISPLAY SYSTEM (SPDS)

SCHEDULE B - 15 ITEMS

  • NRC COMMITMENTS Q LIST RCP THERMAL BARRIERS SURRY
  • NRC INTEREST OR INVOLVEMENT REQUIRED PRZ SAFETY AND RELIEF VALVE MODS CORE UPRATING Ul SG/RCP SNUBBER REPLACEMENT SPENT FUEL FACILITY
  • NO NRC INVOLVEMENT REQUIRED L.P. TURBINE REFURBISHMENT P 250 COMPUTER REPLACEMENT STATION PERSONNEL FACILITY MOD.

FW HTR BUNDLE REPLACEMENT RAD\\~ASTE FACILITY VITAL BUS MODS SPENT RESIN TANK MODS SG INSTRUMENTATION MONITORING SYSTEM TRAINING CENTER EXPANSION 77-RWC-2148B

e NORTH ANNA SCHEDULE B - 18 ITEMS

  • NRC COMMITMENTS Q LIST
  • NRC INTEREST OR INVOLVEMENT REQUIRED BORIC ACID CONCENTRATION REDUCTION SL~ SYSTEM IMPROVEMENTS SW SYSTEM PIPE CLEANING PRZ SAFETY AND RELIEF VALVE MODS SG/RCP SNUBBER REPLACEMENT REACTOR TRIP BELOW 30% POWER CORE UPRATING
  • NO NRC INVOLVEMENT REQUIRED L. P. TURBINE REFURBISHMENT LAKE ANNA DEMINERALIZER P 250 COMPUTER SG MANWAY MODS FUEL TRANSFER SYSTEM MODS SG SLOWDOWN IMPROVEMENTS RV HEAD SHIELD FW HTR BUNDLE REPLACEMENT FLOOD CONTROL MODS RADWASTE FACILITY 77-RWC-21488
  • e 1986 - 1988 CAPITAL BUDGET OVERVIEW
  • SURRY 1986 1987 1988 TOTAL 58.8 49.7
51. 3 SCHEDULE A 18.3 4.6 1.4 SCHEDULE B 31.1 15.8 27.4 OTHER 9.4 29.3 22.5
  • NORTH ANNA TOTAL 54.7 52.9 51.2 SCHEDULE A 10.4 10.0 0.1 SCHEDULE B 30.2 29.3 31.3 OTHER 14.1 13.6 19.8 77-RWC-2148B *

.ROPOSED REVIEW SCHEDULE *

-SUBMITTAL OF SURRY AND NORTH ANNA LICENSE AMENDMENTS AND nPLANn

-MEET WITH NRC TO DISCUSS AND CLARIFY SUBMITTAL

-OBTAIN INFORMAL AGREEMENT ON ACCEPTABILITY OF LICENSE AMENDMENT AND uPLANn

-SUBMIT DRAFT IMPLEMENTATION SCHEDULES

-MEET, AS REQUIRED, TO DISCUSS IMPLEMENTATION SCHEDULES

-SUBMIT FINAL IMPLEMENTATION SCHEDULE

-OBTAIN LICENSE AMENDMENT 77-RWC-20958-4 12/85 1/86 2/86 3/86 3-6/86 7/86 8/86

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