ML18142A184

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Summary of 850205 Meeting W/Util to Brief Incoming Director of Div of Licensing Re Status & Licensing Activities
ML18142A184
Person / Time
Site: Surry  Dominion icon.png
Issue date: 02/11/1985
From: Neighbors J
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8502200150
Download: ML18142A184 (21)
v • d • e


Text

-- -~----

e February 11, 1985

  • Docket Nos. 50-280 and 50-281 LICENSEE: Virginia Electric and Power Company (VEPCo)

FACILITY: Surry Power Station, Units 1 and 2

SUBJECT:

SUMMARY

OF MEETING HELD ON FEBRUARY 5, 1985, TO BRIEF INCOMING DIRECTOR, DIVISION OF LICENSING, ON STATUS AND LICENSING ACTIVITIES RELATED TO SURRY POWER STATION Mr. Hugh L. Thompson, Jr., who has recently become Director, Division of Licensing, requested that each project manager, brief him on the status of their plants. The licensee, Regions and other staff members were also invited to participate in the meeting.

A list of attendees is enclosed.

The project manager's presentation included a brief description of the Surry Power Station, location, plant status, hearings and other licensing activities.

An outline of the presentation is enclosed.

The licensee's representatives provided additional details relating to the VEPCO organization and an overview of the facility and current activities.

Subsequent to the initial presentations, scheduling, time required to complete licensing actions, priority of activities, problems and areas where improvements could be implemented to enhance the licensing process were discussed Mr. Thompson thanked all participants and indicated his interest in current and future licensing activities related to the Surry Power Station.

He further indicated his availability to all parties to assist in assuring all licensing activities receive proper and timely resolution.

Enclosure:

As stated cc w/enclosure:

See next page OliL D

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/s/JDNeighbors Joseph D. Neighbors, Project Manager Operating Reactors Branch #1 Division of Licensing

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MEETING

SUMMARY

DISTRIBUTION OPERATING REACTORS 8RANCR NO. 1 Docket or Central File NRC PDR Local PRO ORB# 1 Rdg J. Partlow (Emergency Preparedness only)

Steve Varga Project Manager OELD E. Jordan P. McKee ACRS (10)

NSIC Gray File Plant Service List CParrish JPartlow NRC Participants

Docket Nos. 50-280 and 50-281 e

e UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 February 11, 1985 LICENSEE: Virginia Electric and Power Company (VEPCo)

FACILITY: Surry Power Station, Units 1 and 2

SUBJECT:

SUMMARY

OF MEETING HELD ON FEBRUARY 5, 1985, TO BRIEF INCOMING D!RECTOR, DIVISION OF LICENSING, ON.STATUS AND LICENSING ACTIVITIES RELATED TO SURRY POWER STATION Mr. Hugh t. Thompson, Jr., who has recently become Director, Division of

  • *- Licensing~ requested that each project manager, brief him on the status of thei~ plants.-* The licensee, Regions and other staff members were also invited to participate in the meeting. A list of attendees is enclosed.

The project manager's presentation included a brief description of the Surry Power Station, location, plant status, hearings and other licensing activities.

An outline of the presentation is enclosed.

The licensee's representatives provided additional details relating to the VEPCO organization and an overview of the facility and current activities.

Subsequent to the initial presentations, scheduling, time required to complete licensing actions, priority of activities, problems and areas where improvements could be implemented to enhance the licensing process were discussed Mr. Thompson thanked all participants and indicated his interest in current and future licensing activities related to the Surry Power Station.

He further indicated his availability to all parties to assist in assuring all licensing activities receive proper and timely resolution.

Enclosure:

As stated cc w/enclosure:

See next page

~-~~anager Operating Reactors Branch #1 Division of Licensing

Mr. W. L. Stewart Virginia Electric and Power Company cc:

Mr. Michael W. Maupin Hunton and Wi 11 i ams

  • Post Office Box 1535 Richmond, Virginia 23213 Mr. Robert F. Saunders, Manager Post Office Box 315 Surry, Virginia 23883 Donald J. Burke, 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 Regional Radiation Representative EPA Region II I Curtis Buildinq - 6th Floor 6th and Walnut-Streets Philadelphia, Pennsylvania 19106 Mr. J. H. Ferguson Executive Vice President - Power Virginia Electric and Power Company Post Office Box 26666 Richmond, Virginia 23261 James P. O'Reilly Regional Administrator - Region II U.S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 James B. Kenley, M.D., Commissioner Department of Health 109 Governor Street Richmond, Virginia 23219 e

Surry Power Station Units 1 and 2 Attorney General 1101 East Broad Street**

Richmond, Virginia 05602

H. Thompson D. Neighbors J. Miller R. Brady

.W. Stewart

  • R. Hardwick N. Clark LIST OF ATTENDEES NRC NRC NRC NRC VEPCO VEPCO VEPCO

e PLANT NAME:

Surry Power Station 1 and 2 UTILITY: Virginia Electric and Power Co. (VEPCO)

PROJECT MANAGER, BRANCH: Don Neighbors, ORB#! X24837 STATUS:

Operating LICENSING ISSUES:

1.

Environmental Qualification

2.
a.

NRC action to be completed soon (SER)

b.

Surry mods to be completed next refueling outage (March 1985) for Unit 2.

Unit 1 completed by 3/31/85 Appendix R *

a.

NRC reviewing requests for exemption

b.

VEPCO has performed many mods with work continuing

3.

NUREG 0737

a. modifications essentially completed
b.

EOF & TSC essentially complete except for SPDS Items of Interest

1. Steam Generators
a.

Surry was the first plant to replace steam generators

b.

Surry replaced condensers

c. Surry added full flow demineralization system to secondary side
2.

Fuel Storage

a. Surry spent fuel pool is almost full
b.

Dry storage facility is under review by MMSS

c. Shipments to North Anna and DOE are planned Average Time to Complete Licensing Actions:

MPAs Surry 1 57.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Surry 2 44.o hours SALP:

SALP rating licensing 1 Appraisal Period - 9/1/83 - 2/28/85 Board Meeting - 4/23/85 Licensee Meeting - 5/3/85 Tentative

3

8.

Refueling - Category 1

9.

Licensing Activities - Category 1

10.

Quality Assurance Program-* Category 2 D.

Overall Facility Evaluation - Surry 1 and 2 Acceptable performance by the licensee at-the pi ant level was observed.

Major strengths were identified in the areas of surveillance, emergency preparedness, security and safeguards, refueling, and licensing activities.

One major weakness was identified in the area of radiological controls.

Although not identified as a weakness, it should be noted that perfor~

mance in the area of plant operations had declined from the prevjous a*ssessment period.

Improvements in performance from the previous

  • and licensing activities.

E.

Facility Performance - Surry 1 and 2 Tabulation of ratings for each functional area:

1.

Plant Operations - Category 2

2.

Radiological Controls - Category 3

3.

Maintenance - Category 2

4.

Surveillance - Category 1

5.

Fire Protection - 2

6.

Emergency Preparedness - Category 1

7.

Security and Safeguards - Category 1

8.

Refueling - Category 1

9.

Licensing Activities - Category 1

10.

Quality Assurance Program - Category 2 F.

SALP Board Members:

R. C. Lewis, Director, Division of Project and Resident Programs (DPRP) (Chairman), Region II (RII)

J. P. Stohr, Director, Division of Emergency Preparedness and Materials Safety Programs (DEPMSP), RII H. C. Dance, Chief, Project Branch 2, DPRP, RII S. A. Varga, Chief, Operating Reactors Branch (ORB) 1, Division of Licensing (DL), Office of Nuclear Reactor Regulation (NRR)

G.

SALP Board Attendees:

A. R. Herdt, Chief, Engineering Program Branch, Division of Engineering and Operational Programs (DEOP), RII D. M. Collins, Chief, Emergency Preparedness and Materials Safety Branch, DEPMSP, RII C. M. Upright, Chi~f~ Management Programs Section, DEOP, RII F. Jape, Chief, Test Programs Section, DEOP, RII T. E. Conlon, Chief, Plant Systems Section, DEOP, RII J. J. Blake,.Chief, Materials and Mechanical Section,.DEOP, RII

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e Vice President Nuclear Operations Department W. L~ STEWART Manager *

~ Nuclear Programs and Licensing R. J~ HARDWICK, JR.

Director Safety E*valuation and c*ontrol N. E*. CLARK Supervisor Nuclear Licensing Principle lnterf ace for North Anna D. A. SOMMERS D. J~ FORTIN Principle* lnterf ace for Surry J.D.HEGNER

SURRY 1 F A C I L I T Y D A T A Report Period OCT 1984 FACILITY DESCRIPTION LOCATION STATE ******.** ~ *....**.*. VIRGINIA COUNTY **...*.***. : *.*.... SURRY DIST AND DIRECTION FROM NEAREST POPULATION CTR.*. 17 MI NW OF NEWPORT NEWS, VA TYPE OF REACTQR *****.*.**.* PWR DATE INITIAL CRITICALITY.*. JULY 1, 1972 DATE ELEC ENER 1ST GENER *** JULY 4, 1972 DATE COMMERCIAL OPERATE..*. DECEMBER 22, 1972 CONDENSER COOLING METHOD.*. ONCE THRU CONDENSER COOLING WATER.*.* JAMES RIVER ELECTRIC RELIABILITY COUNCIL ***..***........*. SOUTHEASTERN ELECTRIC RELIABILITY COUNCIL UTILITY & CONTRACTOR INFORMATJQlt UTILITY LICENSEE..*.............. VlRGINIA ELECTRIC&. POWER CORPORATE ADDRESS........ P.O. BOX 26666 RICHMOND, VIRGINIA 23261 CONTRACTOR ARCHITECT/ENGINEER *..**.* STONE & WEBSTER NUC STEAM SYS SUPPLIER... WESTINGHOUSE CONSTRUCTOR............*. STONE & WEBSTER TURBINE SUPPLIER..*...*.. WESTINGHOUSE REGULATORY INFORMATION IE REGION RESPONSIBLE...... II IE RESIDENT INSPECTOR...... D. BURKE LICENSING PROJ MANAGER..... D. NEIGHBORS DOCKET NUMBER............ 50-280 LICENSE & DATE ISSUANCE.... DPR-32, MAY 25, 1972 PUBLIC DOCUMENT ROOM....... SWEM LIBRARY COLLEGE OF WILLIAM AND MARY WILLIAMSBURG, VIRGINIA 23185 I N S P E C T I O N S T A T U S

  • INSPECTION

SUMMARY

+ INSPECTION AUGUST 1~31 (84-24>*

THIS INSPECTION INVOLVED 75 INSPECTOR-HOURS ON SITE IN THE AREAS OF PLANT OPERATIONS AND

. OPERATING RECORDS, PLANT MAINTENANCE AND SURVEILLANCE, PLANT SECURITY, AND FOLLOWUP OF EVENTS.

IN THE AREAS INSPECTED, TWO VIOLATIONS WERE IDENTIFIED; FAILURE TO FOLLOW PROCEDURES DURING REPLACEMENT OF AN RPS RELAY - PARAGRAPH 6.D; 10 CFR 50.59 SAFETY EVALUATION NOT PERFORMED/DOCUMENTED FOR CHANGE TO FACILI.TY AS DESCRIBED IN FSAR. - PARAGRAPH S.E.

INSPECTION SEPTEMBER 1-28 (84-26):

THIS INSPECTION INVOLVED 102 INSPECTOR-HOURS ON SITE IN THE AREAS OF PLANT OPERATIONS AND*

OPERATING RECORDS, PLANT MAINTENANCE AND SURVEILLANCE, PLANT SECURITY, FOLLOWUP OF EVENTS, AND LICENSEE EVENT REPORTS.

IN THE AREAS INSPECTED, NO VIOLATIONS OR DEVIATIONS WERE IDENTIFIED.

INSPECTI~N SEPTEMBER 19-20 (84-27):

THIS ROUTINE, ANNOUNCED INSPECTION INVOLVED 40 INSPECTOR-HOURS ON SITE DURING NORMAL DUTY HOURS IN THE AREAS OF AN*EMERGENCY PREPAREDNESS EXERCISE.

OF THE AREAS INSPECTED, NO VIOLATIONS OR DEVIATIONS WERE IDENTIFIED.

INSPECTION SEPTEMBER 24-28 (84-28):

THIS ROUTINE, UNANNOUNCECD INSPECTION ENTAILED 14 INSPECTOR-HOURS ON SITE CTHO HOURS ON BACKSHIFT) INSPECTING; SECURITY PROGRAM AUDIT; TESTING AND MAINTENANCE; PHYSICAL BARRIERS - PROTECTED AND VITAL AREAS; ACCESS CONTROL - PERSONNEL, PACKAGES, AND VEHICLES; AND A COMPREHENSIVE REVIEW OF THE PROTECTION AFFORDED VITAL EQUIPMENT IDENTIFIED IN THE LICENSEE'S PHYSICAL SECURITY PLAN CPSP), THE LOS ALAMOS NATIONAL LABORATORY CLANL> VITAL AREA DEFINITION REPORT AND THE NRC REGULATORY EFFECTIVENESS REVIEW REPORT CRER).

ONE VIOLATION WAS IDENTIFIED*~ FAILURE TO PERFORM A HANDS-ON SEARCH OF A VISITOR PRIOR TO ENTRY INTO THE PROTECTED AREA.

PAGE 2-328 e

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SURRY 2 FA CI LI.TY DAT A Rapart Period OCT 1984 FACILITY DESCRIPTION LOCATION STATE.******...**..**.*.* VIRGINIA COUNTY ***** ~.****. ! ****** SURRY DIST AND DIRECTION FROM NEAREST POPULATION CTR..* 17 MI NW OF NEWPORT NEWS. VA TYPE OF REACTOR *.*.*..***** PWR DATE INITIAL CRITICALITY *.. HARCH 7. 1973 DATE ELEC ENER 1ST GENER... MARCH 10. 1973 DATE COM~ERCIAL OPERATE.**. HAY 1. 1973 CONDENSER COOLING HETHOD.*. ONCE THRU

  • CONDENSER COOLING HATER..** JAMES RIVER ELECTRIC RELIABILITY COUNCIL..**...*.....****. SOUTHEASTERN ELECTRIC RELIABILITY COUNCIL UTILITY a CONTRACTOR INFORMATION UTILITY LICENSEE.***.******.*.*** VIRGINIA ELECTRIC & POWER CORPORATE ADDRESS *..*.*** P.O. BOX 26666 RICHMOND. VIRGINIA 23261*

CONTRACTOR ARCHITECT/ENGINEER.....*. STONE & WEBSTER NUC STEAM SYS SUPPLIER *.* HESTIN~HOUSE CONSTRUCTOR..*.****...*.. STONE & WEBSTER TURBINE SUPPLIER ***....*. WESTINGHOUSE REGULATORY INFORMATION IE REGION RESPONSIBLE.****. II IE RESIDENT INSPECTOR..*..* D. BURKE LICENSING PROJ MANAGER.**.* D. NEIGHBORS DOCKET NUMBER........**.* 50-281 LICENSE a DATE ISSUANCE **.* DPR-37. J~NU~RY 29. 1973 PUBLIC DOCUMENT ROOM **.*..* SWEM LIBRARY COLLEGE OF WILLIAM AND MARY WILLIAMSBURG. VI~GINIA 23185 I N S P E C T I D N S T A T U S INSPECTION

SUMMARY

+ INSPECTION AUGUST 1-31 <&4-24)2 THIS INSPECTION INVOLVED 75 INSPECTOR-HOURS ON SITE IN THE AREAS OF PLANT OPERATIONS AND OPERATING RECORDS, PLANT MAINTENANCE AND SURVEILLANCE, PLANT SECURITY, AND FOLLOWUP OF EVENTS.

IN THE AREAS INSPECTED, TWO VIOLATIONS HERE IDENTIFIED; FAILURE TO FOLLOW PROCEDURES DURING REPLACEMENT OF AN RPS RELAY - PARAGRAPH 6.D; 10 CFR 50.59 SAFETY EVALUATION HOT PERFO~~ED/DOCUMENTED FOR CHANGE TO FACILITY AS DESCRIBED IN FSAR - PARAGRAPH 5.E.

INSPECTION SEPTEMBER 1-28 (84-26):

THIS INSPECTION INVOLVED 102 INSPECTOR-HOURS ON SITE IN THE AREAS OF PLANT OPERATIONS AND OPERATING RECORDS, PLANT MAINTENANCE AND SURVEILLANCE, PLANT SECURITY, FOLLOWUP OF EVENTS, AND LICENSEE EVENT REPORTS.

IN THE AREAS INSPECTED, NO VIOLATIONS OR DEVIATIONS WERE IDENTIFIED. 1 IHSPECTION SEPTEMBER 19-20 (84-27) I THIS ROUTINE, ANNOUNCED I'NSPECTION INVOLVED 40 rnsPECTOR-HOURS ON SITE DURING :NORMAL DUTY HOURS JU THE AREAS 0~ AN EMERGENCY PREPAREDNESS EXERCISE.

OF THE AREAS INSPECTED, NO VIOLATIONS OR DEVIATIONS WERE IDENTIFIED.

INSPECTION SEPTEMBER 24'-28 C84-28):

THIS ROUTINE, UNANNOUNCECD INSPECTION ENTAILED 14 INSPECTOR-HOURS ON SITE CTWO HOURS ON BACKSHIFT) INSPECTING; SECURITY PROGRAM AUDIT; TESTING AND MAINTENANCE; PHYSICAL BARRIERS - PROTECTED AND VITAL AREAS; ACCESS COHTROL - PERSONNEL, PACKAGES, AND VEHICLES; AND A COMPREHENSIVE REVIEW OF THE PROTECTION AFFORDED VITAL EQUIPMENT IDENTIFIED IN THE LICENSEE'S PHYSICAL SECURITY PLAN (PSP), THE LOS ALAMOS NATIONAL LABORATORY CLANL) VITAL AREA DEFINITION REPORT AND THE NRC REGULATORY EFFECTIVENESS REVIEW REPORT CRER>.

ONE VIOLATION HAS IDENTIFI~D - FAILURE TO PERFORM A HANDS-ON SEARCH OF A VISITOR PRIOR TO ENTRY INTO THE PROTECTED AREA.

e e

PAGE 2-334

  • -~z.*it.:~i~

....,~.

R-1208687-001 T E C H N I C A L A S S I G N M E N T C O N T R O L S Y S T E M C o*N DENSE D MAN AGE MEN T REPORT (HEADQUARTERS)

PAGE tlO.:

147 RUN DATE: 12/ 1 l/84 FACILITY: SURRY 1 PLANT LOCATION: 17 MI NW OF NEWPORT NEWS, VA DOCKET NUMBER=

050-00280 LICENSED POWER: 2441 MWT DESIGN POWER:

0788 MWE ARCH/ENGINEER:

S&W NSSS VENDOR:

WEST IE INSPECTOR:

D. BURKE

        • ACTIVE ISSUES****

EXEMPTIONS TOT APPENDIX R (7/6/84)

FUEL HANDLING ACCIDENT INSIDE CONTAINMENT HIGH ENERGY BREAK INSPECTION PROGRAM T.S. 4.15-A REORGAIHZATION ASME XI RELIEF REQUEST (12/83)

ADEQUACY OF STATION ELECTRIC DISTRIBUTION SYSTEM VOLTAGES DELETE ROD DROP TIMES AT COLD SHUTDOWN NUREG-0737 II.K.3.30, SB LOCA OUTLINE.

REACTOR COOLANT PUMP TRIP ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL IST SECOND TEN YEAR INTERVAL CONTROL OF HEAVY LOADS - PHASE* II CFOLLOWUP OF MPAIC-10)

ITEM 1.1 - POST TRIP REVIEW PROGRAM DESCRIPTION AND ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTACHMENT FOR ITEM 2.1 - EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE -

ITEMS 3. 1. 1 8 3. 1. 2 - POST MAINTENANCE TESTING ITEM 3.1.3 -POST-MAINTENANCE TESTING-CHANGES TO TECH REACTOR TRIP SYSTEM RELIABILITY - VENDOR RELATED MASONRY WALL DESIGN. RESPONSE TO IE BULLETIN 80-11

    • UNSCHEDULED ISSUES**

NUREG-0737 I.C.1.3A, ABNORMAL TRANSIENT OPERATOR GUIDELINES RV AND SV TESTING NUREG-0737 II.F.2.3, INADEQUATE CORE COOLING INSTRUMENTATION NUREG-0737 III.A. 1. 2, TECHNICAL SUPPORT CENTER NUREG-0737 III.A.1.2, OPERATIONAL SUPPORT CENTER NUREG-0737 III.A.1.2, EMERGENCY OPERATIONS FACILITY NUREG-0737 III.A.2.2, METEOROLOGICAL DATA UPGRADE IWREG 0737 II.K.3.31 COMPLIANCE WITH 10 CFR S0.46 DRY CASK INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDENT CRG I.D.2. SAFETY PARAMETER DISPLAY SYSTEM ITEMS 4.2.1 8 4.2.2 - PREVENTATIVE MAINTENANCE PROGRAM FOR ITEM 1. 1 - POST TRIP REVIEW-DATA AND INFORMATION CAPABILITY ITEM 2.2 - EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE -

ITEIIS 3.2.1 8 3.2.2 - POST-MAINT TESTING PROCEDURES AND ITEi! 3.2.3 - POST-MAINTENANCE TESTING -CHANGES TO TECH.

ITEMS 4.2.3 & 4.2.4-PREVENTATIVE MAINTENANCE PROGRAM FOR RX TAC MPA NUMBER tlO.

M55332 M08620 M43113 M48118 M53359 M53533 M55938 M45866 M4968 1

  • M42468 M49144 M52276 M52805 M53198 M52886 M52967 M5304&

M53103 M42867 M44342 M44622 M45173 M45985 M46056 M46128 M46344 M48206 M49148 MS 1138 MS1288 MS3156 MS3638 M53721 M53804 M53887 M53943 C-07 F-57 G-01 B-60 C-15 B-76 B-82 B-77 B-78 B-79 B-80 B-59 F-05 F-14 F-26 F-63 F-64 F-65 F-68 F-58 A-17 F-09 B-81

  • PRQJECT MANAGER: D. NEIGHBORS BRANCH CHIEF:

S. VARGA LIC. ASSISTANT:

C. PARRISH RAI DATE

. RAI

RESPONSE

DATE 09/15/84 06/06/84C 07/12/84C 06/22/84C 08/31/84 09/30/84 02/28/85 TER DATE 12/ 12/84 02/02/85 SE INPUT DATE LIC ACT A

_RA.IL 9 12/ 15/84 12/31/84 12/31/8ft 12/31/84 12/31/84 12/31/84 01/01/85 01/30/85 0l/31/85 02/15/85 02/28/85 03/31/85 05/01/85 06/01/85 09/30/85 09/30/85 09/30/85 O'J/30/85 12/31/87

TE.CH NI CAL ASSIGNMENT CONTROL SYSTEM C O N D E N S E D M A N A G E M E N T R E P O R T

<HEADQUARTERS)

FACILITY: SURRY 1 Ttllf

  • ~ UHSCHEDULED ISSUES MM

<CONTINUATION)

ITEIIS 4.5.2 & 4.5.3 -

REACTOR TRIP SYSTEM FUNCTIONAL TE5TING IT Ell lj. 5. I -

REACTOR SYSTEM FUNCTIONAL CAPABILITY EliEf:GEIICY EXERCISE EXEMPTION ITE:i (1.3CTS) - AUTOMATIC ACTUATION OF SHUNT TRIP FOR WAND STAnlUP CERTIFICATION PROGRAM.

TECH. SPECS. AFFECTED BY 50.72 AND 50.73 CGL 83-43)

DIESEL GEllERATOR RELIABILITY TECH. SPECS. (GL 84-15)

RELOAD DESIGN AUDIT I.D. 1.2 DETAILED CONTROL ROOM DESIGN REVIEW

SUMMARY

REPORT -

EXTEHSIOH TO ENVIRONMENTAL QUALIFICATION OF ELECTRICAL

      • COMPLETED ISSUES MMM I. D. 1. I - DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN CHAP.GI!IG PU!lP TECH SPECS AFWS - CHAHGE OPERABLE TO AVAILABLE REACTOR VESSEL COOLANT LEVEL MONITOR RCS VfllTS TECHIIICAL SPECIFICATIOHS NUREG 073 ITEM II. B. 1 H:CHIHCAL SPECIFICATIDHS COVERED BY GENERIC LETTERS 83-36, LIFT ORDER TD SHOW CAUSE DATED MARCH 13, 1979 RAI TAC MPA RAI

RESPONSE

NUMBER llih J1AIE DATE M54031 M54114 M55065 M55380 M55541 M55745 A-18 M55908 D-19 M56079 M56170 F-71 M56389 M51208 F-08 08/10/84 08/30/85 M49493 M54742 M51371 M54418 M54573 B-83 M53492 TER

.M.I.f PAGE NO. 1 148 RUN DATE: 12/11/84 SE INPUT

__!2lli LIC ACT DATE 10/10/84C 10/12/84C 10/12/84C 10/ 15/84C 10/ 15/84C 10/15/84C 10/31/84C e

"U I TECHNICAL ASSIGNMENT CONTROL

  • SYSTEM C O N D E N S E D M A N A G E M E N T R E P O R T

<HEADQUARTERS>

FACILITY: SURRY 2 T T l I,.

n 1111::;c:HEDULED ISSUES JOE CCONlINUATION)

IT[M 5 2.3 - POST-MAINTENANCE TESTING -CHANGES TO TECH.

Ill:il:, <i.2.3 & 4.2.4-PREVENTATIVE MAINTENANCE PROGRAM FOR RX lltM3 **.5.2 & 4.5.3 -

REACTOR TRIP SYSTEM FUNCTIONAL TESTING IT £:11 4. 5. I - REACTOR SYSTEM FUNCTIONAL CAPABILITY ITEM ~.3CTS> - AUTOMATIC ACTUATION OF SHUNT TRIP FOR WAND STARTUP CERTIFICATION PROGRAM TECH. SPECS. AFFECTED BY 50.72 AND S0.73 CGL 83-43)

DIESEL GEIIERATOR RELIABILITY TECH. SPECS. CGL 84-15)

RELOAD,EsIGN AUDIT I.D. 1.2 DETAILED CONTROL ROOM DESIGN REVIEW

SUMMARY

REPORT -

      • COMPLETED ISSUES***

I.D. 1.1 - DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN CHARGING PUMP TECH SPECS AFHS - CHANGE OPERABLE TO AVAILABLE REACTOR VESSEL COOLANT LEVEL MONITOR RCS VEHTS TECHNICAL SPECIFICATIONS NUREG 073 ITEM II.B. 1 TECHNICAL SPECIF~CATIONS COVERED BY GENERIC LETTERS 83-36, TAC MPA NUMBER fill..

M53888 M53944 M54032 M54115 M55381 M55542 MS5746 A-18 M55909 D-19 M56080 M56171 F-71 RAI

~

RAI

RESPONSE

DATE MS1209 F-08 08/10/84 08/30/BS M49494 M54743 M51372 M54419 MS4574 B-83 TER DATE PAGE NO.:

150 RUN DATE: 12/111'84 SE INPUT

_M.If LIC ACT DATE 10/10/84C 10/12/84C 10/12/84C 10/15/84C 10/1S/84C 10/ 1S/84C

R-1208687-001 T E C H N I C A L A S S I G N M E N T C O N T R O L S Y S T E M C O N D E N S E D M A N A G E M E N T R E P O R T CHEADQUARTERS)

FACILITY: SURRY 2 PLANT LOCATION: 17 MI NW OF NEWPORT NEWS, VA LICENSED POWER: 2441 Ml-IT

  • PROJECT MANAGER:

DOCKET NUMBER:

050-00281 DESIGN POWER:

0788 MWE BRANCH CHIEF:

ARCH/ENGINEER:

S&W NSSS VENDOR:

WEST LIC. ASSISTANT:

IE INSPECTOR:

D. BURKE RAI TAC MPA RAI

RESPONSE

TER

.I.!I.li NUMBER NO.

.M.IJ;;

DATE Mif ioE:IE* acTivi; ISSUES 3E3El0£ ISi -

SECOND TEN YEAR INTERVAL M49143 EMERGENCY EXERCISE EXEMPTIOf~

M55066 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT M08619 C-07 03/07/77C HIGH ENERGY BREAK INSPECTION PROGRAM TECH SPEC 4. 15-A M43114 09/15/84 REORGANIZATION M48119 ASME XI RELIEF REQUEST (12/83)

M53360 06/06/84C 07/21/84 ADEQUACY OF STATION ELECTRIC DISTRIBUTION SYSTEM VOLTAGES M53534 EXEMPTIONS TO APPENDIX R (7/6/84)

M55333 DELETE ROD DROP TIMES AT COLD SHUTDOWN M55939 NUREG-0737 II.K.3.30, SB LOCA OUTLINE M45867 F-57 REACTOR COOLANT PUMP TRIP M49682 G-01 IST -

SECOND TEN YEAR INTERVAL M49145 06/22/84C CONTROL OF HEAVY LOADS - PHASE II CFOLLOHUP OF MPAIC-10)

M52277 C-15 ITEM 4.3 - AUTOAMTIC ACTUATION OF SHUNT TRIP ATTACHMENT FOR M53199 B-82 D.

s.
c.

ITEM 1.1 - POST TRIP REVIEW PROGRAM DESCRIPTION AND M52806 B-76 12/ 12/84 ITEM 2.1 -

EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE -

M52887 B-77 ITEMS 3.1.1 & 3.1.2 - POST MAINTENANCE TESTING M52968 B-78 ITEM 3.1.3 -POST-MAINTENANCE TESTING-CHANGES TO TEC~

M53049 B-79 REACTOR TRIP SYSTEM RELIABILITY -

VENDOR RELATED M53104 B-80

    • UNSCHEDULED ISSUES**

ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL M42469 B-60 MASONRY WALL DESIGN. RESPONSE TO IE BULLETIN 80-11 M42868 B-59 08/31/84 09/30/84 NUREG-0737 I.C.1.3A, ABNORMAL TRANSIENT OPERATOR GUIDELINES M44343 F-05 02/02/85 RV AND SV TESTING M44623 F-14 NUREG-0737 II.F.2.3, INADEQUATE CORE COOLING INSTRUMENTATION M45174 F-26 NUREG-0737 III.A.1.2, TECHNICAL SUPPORT CENTER M45986 F-63 NUREG-0737 III.A.1.2, OPERATIONAL SUPPORT CENTER M46057 F-64 NUREG-0737 III.A.1.2, EMERGENCY OPERATIONS FACILITY M46129 F-65 NUREG-0737 III.A.2.2, METEOROLOGICAL DATA UPGRADE M46345 F-68 NUREG 0737 II.K.3.31 COMPLIANCE WITH 10 CFR 50.46 M48207 F-58 DRY CASK INDEPENDENT SPENT FUEL STORAGE INSTALLATION M49149 INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDENT CRG MS 1139 A-17 I.D.2. SAFETY PARAMETER DISPLAY SYSTEM M51289 F-09 ITEMS 4.2. 1 & 4.2.2 - PREVENTATIVE MAINTENANCE PROGRAM FOR M53157 B-81 ITEM 1.1 - POST TRIP REVIEW-DATA AND INFORMATION CAPABILITY M53639 ITEM 2.2 -

EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE -

M53722 ITEMS 3.2.1 & 3.2.2 - POST-MAINT TESTING PROCEDURES AND M53805 PAGE NO. :

149 RUN DATE: 12/ 11/84 NEIGHBORS VARGA PARRISH SE IHPUT LIC ACT J!A.If

__DATE 09/15/84 09/30/84 12/31/84 12/ 31/84 12/31/84 12/31/84 12/31'/84 12/31/84 0 l/0 1/85 0 1/30/85 01/31/85 02/28/85 03/31/85 06/01/85 09/30/85 O'J/30/85 09/30/85 09/30/85 09/30/85 e

e

SURRY LICENSING ISSUF;S 0 TECHNICAL SPECIFICATION UPGRADE 0 EQUIPMENT QUALIFICATION 0 NUREG 0737 0 INDEPENDENT SPENT FUEL STORAGE INSTALLATION NORTH ANNA LICENSING ISSUES 0 DlESEL.GENERATORS 0 SERVICE WATER SYSTEM UPGRADE 0 TRANSSHIPMENT OF SURRY SPENT FUEL TO NORTH ANNA

~CORE THERMAL UPRATING 0 RES0LVE LICENSING ISSUES BACKLOG COMMON ISSUES 0 INTERGRATED LIVING SCHEDULE 0 STEAM GENERATOR MAINTENANCE AGREEMENT 0 SOLID RADWASTE STORAGE FACILITY 0 BORIC ACID REDUCTION 0 APPENDIX R 0 10 MOST SIGNIFICANT ISSUES 0 0PERATOR TRAINING 0 NUMARC ISSUES MEJ /ogw /LMS-010

_./

e e

10 MOST SIGNIFICANT ISSUES FOR 1985

1.

Spent Fuel:

Resolve issues, define storage programs, including participation in the Department of Energy Cooperative Agreement, and schedules for. removing spent fuel from the Surry spent fuel pool.

License and upgrade the spent fuel pool at North Anna to increase storage capacity.

2. Facilities:

Establish a

program for upgrading station facilities, including construction* of a new Administration Building at Surry.

Implement the Control Room Design Review (NUREG 0700) and the Emergency Response Capabilities Facilities requirement.

3.

Electrical Systems:

Implement the Electrical Steering Committee's recommendation for

  • resoiving GDC-17 deficiencies and removing existing* restrictions and
  • *
  • l:lJJiitations necessary to improve voltage levels to acceptable values under certain conditions.
4.

Service Water:

Implement plan to reduce the corrosive action of the North Anna Service water.

Specific improvements includ~:

A.

B. c.

D.

E.

F.

G.

H.

I.

J.

K.

L.

M.

Service Water Reservoir Upgrade.

Hot Pipe Penetration Wall Cooler Modifications.

Service Water Chemical Treatment Program.

Service Water System Pipewall Degradation Monitoring Program.

Compensatory Measures.

Service Water Header Cathodic Protection System Replacement.

Service Water System Cleaning.

Coating of Pumps and Heat Exchangers.

Pump House Component Degradation Surveys.

Header Coating Refurbishment.

Isolation Valve Upgrade.

Service Water Technical Specification Revision Based on Reliability Analysis.

Annual Management Report.

5.

Secondary System Performance:

Establish and implement a

program to improve secondary system performance.

Specific areas to investigate include:

A.

Blowdown Recovery (North Anna)

B.

Instrumentation including in-line Chemistry System.

C.

Feedwater Control.

D.

MSRs E.

Condenser leaks.

F.

Feedwater Heater Tube Leaks.

G.

Chemistry H.

Condensate Polishing (North Anna)

I.

Upgrade makeup and condensate water quality.

J.

Examine replacement of copper alloys in secondary systems.

e

6.

Reactor Trips:

Establish a program to investigate the cause of unplanned reactor trips and provide recommendations for reducing the frequency of trips.

7.

Inservice Inspections.and Maintenance Programs:

A.

Develop and implement a comprehensive Inservice Inspection Program at each station.

B.

Revi.se and standardize station maintenance programs to include

, preventive, predictive and corrective sections as balanced portions of the programs.

8.

Reactor Coolant Activity Levels:

.Establish a program to reduce RCS activity by enhanced debris and chemistry ~ontrols and improved fuel quality.

9 ** Kadiation Protection Plan:

Implement the revised Radiation Protection Plan.

10.

Safety and Licensing:

A.

Upgrade the commitments management process.

B.

Upgrade the independent review process.

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