ML18151A896

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Summary of 911022 Meeting W/Util at VEPCO Corporate Ofc Re Component Cooling Water Sys,Dcrdr,Pressurizer Safety Valves, Svc Water Biofouling & Station Blackout Rule.Attendance List & Handouts Encl
ML18151A896
Person / Time
Site: Surry, North Anna  
Issue date: 05/21/1992
From: Buckley B, Engle L
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9206010116
Download: ML18151A896 (88)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 May 21, 1992 Docket Nos. 50-280, 50-281 and 50-338, 50-339 LICENSEE:

Virginia Electric and Power Company {VEPCO)

FACILITIES:

Surry, Units 1 and 2, and North Anna, Units 1 and 2

SUBJECT:

MEETING

SUMMARY

OF COUNTERPARTS MEETING OF OCTOBER 22, 1991 On October 22, 1991, representatives of NRR, Region II and VEPCO met at VEPCO's corporate office to discuss various issues of mutual interest. A list of attendees and handouts are provided in Enclosures 1 and 2, respectively.

Some of the more important issues discussed are described below.

1.

Surry Component Cooling Water (CCW} System VEPCO described their planned modification to the portion of CCW piping associated with the reactor coolant pump (RCP) thermal barriers to provide rupture protection of the CCW piping in the event of failure of an RCP thermal barrier. Planned modifications include two new containment isolation valves, rated at 1500 lbs, and upgrading the applicable piping to 1500 lbs. The current schedule is to implement the modifications during the Unit 1 and Unit 2 refueling outages scheduled for 1992 and 1993, respectively.

The NRC staff found the schedule for the above modifications acceptable.

2.

Surry Detailed Control* Room Design Review (DCRDR)

VEPCO is reassessing the need to complete the remaining 37 DCRDR items.

Upon completion of the reassessment, VEPCO will submit its findings and justification for any proposals to delete any of the previously scheduled modifications.

3.

Surry Pressurizer Safety Valves

4.

VEPCO has elected to modify the safety valves {SVs) by replacing the valve seats with mat~rial that is compatible with a steam environment, and will modify or eliminate the SV loop seals to maintain a steam environment under the SV discs.

North Anna Service Water Biofouling VEPCO, with assistance from the Virginia Institute of Marine Science (VIMS), has selected a biofouling program which will enhance the service water chemical treatment program by controlling sulfate producing bacteria to eliminate microbiological-induced corrosion.

9206010116 920521 PDR ADOCK 05000280

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5. May 21, 1992 Surry Service Water (SW} Biofoulinq In the past, the Surry Power Station encountered difficulty with a significant buildup of hydroids in SW piping resulting in the fouling of safety-related piping and heat exchangers.

To correct this concern, VEPCO, with assistance from VIMS, established a macrofouling control program. Actions taken include sampling of SW and trending results, alternately stagnating the 48" SW headers to reduce oxygen and food transport, and injecting chlorine into the stagnated 48" header.

These actions appear to be effective based upon the inspection of the bearing coolers and the 48" headers which showed no significant marine growth. Other actions underway are described in the attached handouts.

6.

Shutdown Issues VEPCO discussed its nuclear safety policy document pertaining to nuclear safety matters and risks during shutdown.

During shutdown, particular attention is given to critical parameters and on-going activity evolutions, including the use of 10 CFR 50.59 evaluations to enhance plant safety. The staff was favorably impressed with the licensee's sensitivity to safety.

7.

Station Blackout (SBO) Rule The NRC staff informed VEPCO that their SBO submittals for the Surry and North Anna Stations were conceptually satisfactory and suggested that they proceed with ordering the appropriate equipment to facilitate a timely implementation date.

8.

North Anna - MERITS Technical Specifications (TS) Program

9.

The North Anna Station is the lead Westinghouse plant for the MERITS Program.

VEPCO stated that they have essentially put this program on hold until the numerous industry comments have been resolved.

VEPCO also stated that it would cost approximately

. $4xl06 and $6xl06 to adopt this program to the North Anna and Surry Stations, respectively.

Sholly Process The NRC staff gave a presentation of the Shelly process, which VEPCO found to be very informative.

10.

Deliberate Misconduct Rule Mr. Paul Frederickson (Region II) described the new wrongdoers rule involving deliberate misconduct.

The most important part of the discussion pertained to the licensee's need to inform all

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~ T e May 21, 1992 their personnel, contractors and subcontractors, that the NRC can take enforcement action against an individual for any deliberate misconduct that could cause a licensee to violate any NRC rule involving their license.

11.

North Anna Unit 1 Steam Generator Replacement A video animation was presented depicting the steps occurring in the forthcoming NA-1 steam generator (SG) replacement project, presently scheduled to take place in 1995.

Replacement could take place as early as 1993.

Only the lower portions at the SGs will be replaced. Actual replacement is scheduled to require 130 days.

The cost of replacement will be about $185 million. Westinghouse will supply the new SG tube bundles, and Bechtel Power is providing the engineering for the project.

The replaced SG tube bundles will be stored on site. Finally, the licensee plans to conduct the SG replacement program under 10 CFR 50.59.

(Original Signed By)

(Original Signed By)

Bart C. Buckley, Sr. Project Manager Project Directorate II-2 Leon B. Engle, Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

1. List of Attendees
2. Handouts cc w/enclosures:

See next page DISTRIBUTION Docket File NRC & Local PDRs PDII-2 RF T. Murley/F. Miraglia J. Partlow S. Varga G. Lainas H. Berkow B. Buckley L. Engle D. Miller OFC

LA:PDII-2 :PM~I~2 NAME
BBuckley DATE
£ /2J7/92 MTS.SUN OGC E. Jordan, MNBB -3701 M. Branch, RI I P. Frederickson, RII M. Lesser, RII D. Taylor, RII ACRS (10)

J. Wechselberger, 17-G-21

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Virginia Electric and Power Company cc:

Mr. William C. Porter, Jr.

County Administrator Louisa County P.O. Box 160 Louisa, Virginia 23093 Michael W. Maupin, Esq.

Hunton and Williams P.O. Box 1535 Richmond, Virginia 23212 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation P.O. Box 1197 Richmond, Virginia 23209 Old Dominion tlectric Cooperative 4201 Dominion Blvd.

Glen Allen, Virginia 23060 Mr. E. Wayne Harrell Vice President - Nuclear Services Virginia Electric and Power Co.

5000 Dominion Blvd.

Glen Allen, Virginia 23060 Office of the Attorney General Supreme Court Building 101 North 8th Street Richmond, Virginia 23219 Senior Resident Inspector North Anna Power Station U.S. Nuclear Regulatory Commission Route 2, Box 78 Mineral, Virginia 23117 Mr. Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 C.M.G. Buttery, M.D., M.P.H.

State Health Commissioner Office of the Commissioner Virginia Department of Health P.O. Box 2448 Richmond, Virginia 23218 Regional Administrator, RII U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Mr. G. E. Kane, Manager North Anna Power Station P.O. Box 402 Mineral, Virginia 23117 Mr. J. P. O'Hanlon Vice President - Nuclear Operations Virginia Electric and Power Company 5000 Dominion Blvd.

Glen Allen, Virginia 23060 Mr. Martin Bowling Manager - Nuclear Licensing Virginia Electric and Power Co.

5000 Dominion Blvd.

Glen Allen, Virginia 23060 Mr. Michael R. Kansler, Manager Surry Power Station P.O. Box 315 Surry, Virginia 23883 Senior Resident Inspector Surry Power Station U.S. Nuclear Regulatory Commission P.O. Box 166, Route 1 Surry, Virginia 23883 Mr. W. L. Stewart Senior Vice President - Nuclear Virginia Electric and Power Company 5000 Dominion Blvd.

Glen Allen, Virginia 23060

MEITTING

SUMMARY

OF ffiUNI'ERPARTS MEEI'ING OF OCI'OBER 22, 1991

  • ROC'D W/MEM) DID 05/21/92 **** 9206010116

-NOTICE-THE AlTACHED FILES ARE OFFICIAL.

RECORDS OF THE INFORMATION &

REPORTS MANAGEMENT BRANCH.

THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RE-CORDS & ARCHIVES SERVICES SEC-TION P1-22 WHITE FLINT. PLEASE DO

  • NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT FOR REPRODUCTION MUST BE RE-FERRED TO FILE PERSONNEL.

-NOTICE~

,._/II, I

l, Attendance List Meeting With Virginia Electric and Power Company October 22, 1991 H. Berkow M. Branch B. Buckley L. Engle Surry 1&2 and North Anna 1&2 P. Frederickson M. Lesser D. Miller D. Taylor M. Bowling A. Price J. A. Stall D. Benson W. Benthall J. Hegner D. Sommers W. Corbin K. Moore

BRIEFING AGENDA OCTOBER 22, 1991 EMERGENCY RESPONSE ORGANIZATION AUTOMATED NOTIFICATION SYSTEM (EROANS)

1.

SYSTEM CONFIGURATION A.

SYSTEM HARDWARE B.

SITE CONFIGURATION C.

GLOBAL SYSTEM NETWORK

2.

SYSTEM PERFORMANCE A.

DESIGN B.

ATTRIBUTES

3.

IMPLEMENTATION SCHEDULE

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A~1END!1ENT RE,1IEW PROCESS RECEIPT

_ - COMPLETENESS I ACCEPTABILITY REVIEW BY P?vl I

- TYPE OF REVIEW (P!I/TECH STAFF)

- P!I DETER~HNES PRIORITY PREPARE APPROPRIATE NOTICE

- SHOLLY NOTICE (PROPOSED NSHC DETER!HNATION)

.- FEDERAL REGISTER NOTICE

- ENVIRONMENTAL ASSESS. MUST BE PREPARED P!I~ REVIEW OF APPLICATION

- OPEN TAC

- CONSULT WITH TECH STAFF

- *RAI SENT TO LICENSEE, IF NECESSARY

- PREPARE SAFETY EVALUATION FOR AMDT PACKAGE

- CONCURRENCE OF TECH STAFF (OPTIONAL)

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I TECH STAFF REVIEW OF APPLICATION

- PM OPEN TAC

- P11 NEGOTIATE PRIORITY/COMPLETION DATE

-- RAI, IF NEEDED

- TECH STAFF PREPARES SE, I TRANSMITS TO PM

- P~I REVIEWS AND PREPARES A!fDT PACKAGE LICENSING ASSISTANT REVIEW

- CHECK AMDT PACKAGE FOR CO!-fPLETENESS

- CHECK/PREPARE TS PAGES

- CHECK INITIAL NOTICE - EA NEEDED?

CONCURRENCES

- LA, PM, PD, TECH STAFF { OPTIONAL), OGC ISSUE/DENY AMEND!~ENT I I !

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NRC Amendment Review Process NSHC_

Publish I

$holly NSHC

_. or SHC?

Prepare I

Publish environ.

FR Notice SHC -

assessment Applic.

Initial rec'd f-+ review by PM by PM

. 1' PM Take out Prepare Arndt.

package I

TAC SE to typing Deficient PM or submittal

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Tech Letter Staff to licensee review?

SE prepared Arndt.

I PM PM take _. PM negotiate and sent

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... package out TAC date/priority review Tech -

4 I to PM to typing Staff RAI required Request PM sends Licensee sent

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... responds; -

to PM to licensee review continues

i..----------------------

SERVICE LIST/ ADDRESSEE CHANGES

- ANY CHANGES MUST BE SENT BY LETTER TO NRC

- NRC INTERNAL DISTRIBUTION CHANGED

- LICENSING ASSISTANT ENSURES NRR LIST UPDATED AND SENDS CHANGES TO REGION FOR UPDATE

MISCELLANEOUS TOPICS LICENSEE'S NSHC EVALUATION

- MUST EVALUATE ALL CHANGES AGAINST 50.92 STANDARDS

- QUOTED IN STAFF'S SHOLLY NOTICE OATH OR AFFIRMATION - 10 CFR 50.30(b)

- LICENSE APPLICATIONS OR REQUEST FOR AMENDMENTS THEREOF

- RESPONSES TO RAis REGARDING ABOVE I

- RESPONSES TO GENERIC LE'ITERS PURSUANT TO 10 CFR 50.54(f)

I TECHNICAL SPECIFICATIONS PAGE CHANGES

- ANY CHANGES AFTER ORIGINAL SUBMITTAL MUST BE IN WRITING

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- CHANGES TO LICENSE CONDITIONS

- REVISED LICENSE PAGE ISSUED

- SURVEILLANCE TESTING

- -EFFECTIVE DATE VS. IMPLE!fENTATION DATE -

SHOLLY PROCESS ROUTINE NSHC AME~DMENT 30 DAY NOTICE PUBLISHED IN FEDERAL REGISTER

- PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION (NSHC)

- PUBLIC COMMENT /INTERVENTION

- PUBLISHED IN BIWEEKLY SHOLLY NOTICE OR INDIVIDUAL NOTICE

- BEFORE ISSUANCE, NOTIFY STATE OFFICIAL

- ISSUE AMENDMENT AFTER 30 DAYS IF NO INTERVENTION

- NOTICE OF ISSUANCE IN BIWEEKLY SHOLLY NOTICE

- IF INTERVENTION REQUEST RECEIVED:

- FINAL NSHC DETERMINATION

- ADDRESS PROPOSED CONTENTIONS

- NOTIFY STATE OFFICIAL

_-# ISSUE AMENDMENT

- NOTICE OF ISSUANCE

- BIWEEKLY SHOLL Y NOTICE

- INDIVIDUAL NOTICE I I EME~GENCY AMENDMENT - 10 CFR 50.91(a)(5)

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- INVOLVES A SITUATION WHERE FAILURE TO ACT IN A TIMELY WAY

  • . I WOULD RESULT IN DERATING OR SHUTDOWN OF THE PLANT, OR PREVENT RESUMPTION OF OPERATION OR INCREASE OF POWER TO LICENSED POWER LEVEL

- APPLICATION -MUST ADDRESS EMERGENCY CIRCUMSTANCES

- EXPLAIN E1IERGENCY AND WHY IT COULD NOT BE AVOIDED

- PROVIDE NSHC EVALUATION

- STAFF WILL DETERMINE IF LICENSEE FAILED TO MAKE TIMELY APPLICATION

- USUALLY NO TIME FOR PRE~OTICE

- C.LL~ ISSUE AMENDMENT IMMEDIATELY ONLY IF INVOLVES NSHC I

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- STAFF SAFETY EVALUATION* ADDRESSES:

- FINAL NSHC DETERMINATION

- EMERGENCY CIRCUMSTA.~CES

- NOTIFY STATE OFFICIAL

- NOTICE OF ISSUANCE IN BIWEEKLY SHOLLY NOTICE

- ALLOWS PUBLIC 30 DAYS TO REQUEST INTERVENTION

. *)'.:.

- INVOLVES A SITUATION OTHER THAN AN EMERGENtY WHERE SWIFT ACTION IS NECESSARY; I.E., ACTION WOULD RESULT IN NET BENEFIT TO SAFETY

- APPLICATION MUST ADDRESS EXIGENT CIRCUMSTANCES

- EXPLAIN EXIGENCY AND WHY IT COULD NOT BE AVOIDED

- PROVIDE NSHC EVALUATION

- STAFF WILL DETERMINE IF LICENSEE FAILED TO MAKE TIMELY APPLICATION

- INDIVIDUAL NOTICE PUBLISHED IN FEDERAL REGISTER

- PROPOSED NSHC DETERMINATION

- 15 DAYS FOR PUBLIC COMMENT

- 30 DAYS FOR INTERVENTION REQUEST

~ PRESS RELEASE CAN ALSO BE USED

- ISSUE AMENDMENT AFTER 15 DAYS

-. FINAL NSHC DETERMINATION

- ADDRESS EXIGENT CIRCUMSTANCES

- NOTIFY STATE OFFICIAL

- NOTICE OF ISSUANCE IN BIWEEKLY SHOLLY NOTICE SHC AMENDMENT DAY NOTICE PUBLISHED IN FEDERAL REGISTER

- DESCRIPTION OF PROPOSED CHANGES

- INTERVENTION REQUIREMENTS

- ENVIRONMENTAL ASSESSMENT MUST BE PREPARED

- MUST BE PUBLISHED BEFORE ISSUANCE OF AMENDMENT

- ISSUE AMENDMENT AFTER 30 DAYS IF NO INTERVENTION

- NOTICE OF ISSUANCE PUBLISHED IN FEDERAL REGISTER

- IF INTERVENTION REQUEST RECEIVED

- ISSUE AMENDMENT AFTER HEARING COMPLETED, OR

- IF STAFF CAN MAKE PROPOSED NSHC DETERMINATION FOLLOW PROCESS FOR ROUTINE NSHC AMENDMENT

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CCW THERMAL BARRIER MODIFICATIONS SURRY POWER STATION IN 1989 VIRGINIA POWER EXAMINED THE ADEQUACY OF THE CCW SYSTEM WITH REGARD TO A POSSIBLE REACTOR COOLANT PUMP THERMAL BARRIER LEAK.

I DOUBLE CHECK VALVES WERE INSTALLED UPSTREAM ON ALL 3 PUMPS.

DOWNSTREAM ISOLATION WAS AVAILABLE THROUGH AN EXISTING ISOLATION VALVE AT THE PUMP.

PROJECT IS TO UPGRADE THE PENETRATION FOR THERMAL BARRIER RUPTURE PROTECTION BY PROVIDING BOTH AN INBOARD AND OUTBOARD ISOLATION VALVE, UPGRADING THE PIPE CLASS AT THE PENETRATION TO 1500 POUNDS, AND QUALIFYING THE PIPING FROM THE PUMPS TO THE PENETRATION TO 1500 POUND CLASS.

NEW VALVES WILL SERVE AS BOTH CONTAINMENT ISOLATION VALVES ACTIVATED ON SI AND THERMAL BARRIER RUPTURE PROTECTION OF THE PENETRATION.

INSTALLATION WILL BE DURING THE NEXT OUTAGE FOR EACH UNIT (92/93).

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EROANS INNSBROOK TELECOM ROOM

1. MAIN UNIT
2. MONITOR
3. PRINTER
4. MODEMS EROANS NORTH ANNA NANIC TELECOM ROO
1. MAIN UNIT
2. MONITOR
3. PRINTER
4. MODEMS EROANS SURRY SNIC TELECOM ROOM
1. MAIN UNIT
2. MONITOR
3. PRINTER 4
  • MODEMS INNS SECURITY CONTROL ROOM MONITO PRINTER MASTER CONTROLLER EP OFFICE MONITOR PRINTER NAPS SECURITY SS OFFICE MO INTER REMOTE MONITOR W/PRINTER SPS SECURITY SS OFFICE MONITO PRINTER REMOTE MONITOR W/PRINTER f-

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[ TOP 10 SURRY LICENSING TASKS ]

1.

~SMIE SecUon XI ReUef Request. CMle Cmse N498...

Alternate Test Requirements in Lieu of Hydrostatic Testing.

Target Date: 12/15/91

2.

TS241 Opposite Trm~n Opermbmty TestinGJ.. Remove the requirements to test the opposite train when the other train becomes inoperable. Target Date: 11,'25/91 12./zo /11

3.

TS271 Permissivesnnterlocks - Provide Allowed Values for Increasing and Decreasing Permissive Setpoints.

Target Date.: 1 V&'91 1a/zo/'1I

4.

l'S235 ESF linsuumeintmticn U~rm~s... Provide AOTs and LCOs for the ESF and Containment Isolation instruments.

Target Date: 10/31 /91

5.

TS~S7 FAH ~increm~e Stmt !D)INJ~R MsUu@ccl©~©~f... Accomodate increase in radial peaking factors resulting from planned Flux Suppression Inserts installation/provide increased thermal-hydraulic margin for SIF. Target Date: 6/1/92 TS228 3.0/4.0 LCO and Surveillance Requirements - Provide }sus,-,,TrEi::>

additional TS with the 3.0/4.0 applicability. Target Date: 10/15/91 1018 /t:u

6.
7.

GL89-13 Service Water Macrofouling - Resolve Macrofouling & HX} 1ssu£1>

testing issues. Target Date: 09/30/91 101~,q,

8.

TS269 Inoperable, But Trippable, Control Rods - Add Provision for 72 Hour Allowed Outage Time. Target Date: 11 /15/91 12/31 /, 1

9.

TS240 C@intmoinmsint f)e~k Aoou©'.lsint !?rs~tlJre-Revise peak pressure to 45 psi based on current accident analyses. Target Date:

11/1/91 1 O. Surry Radwaste Facility FSAR Submittal - UFSAR Revision Incorporating Facility Description and Notifying NRC per TS 6.9.

Target Date: 10/30/91 Slh~d@we~ mt Uoe !NJ RC Bold at Virginia Power Approved:

J.A. Price M.L. Bowling

I TOP 10 NORTH ANNA LICENSING TASKS I

1.

OlJ[)i)Dft 11

~U@f!llfil\\l @@iro@rrf!lU@rr lf!DD@l~~@O@ OOil~[f)@@UD@iroQ Evaluate need for a mid-cycle inspection. Meet with and provide justification to NRC. Submit TS change if appropriate. Target Date: 12/31/91

2. TS227 RHR Autoc~osurre lnteri@ck Removal. Reduce potential for inadvertent loss of decay heat removal. Target date: 1 O,L81/91. 12/~o/9/
3. TS257 Control Rod Urgent Failure. Extends allowed outage time for corrective maintenance in the event of control failure for multiple rods. Targetdate: -10/a1/91. 12/30/e:,I
4. TS252 Component Cooling Water System Shutdown Mode Requirements.

Adds and clarifies requirements for component cooling water system during cold shutdown and refueling modes.

Target date: 10/31/91.

5. TS259 Increased SI Flow Balance Allowable Flows. Increases acceptable band for SI flow balance testing. Target date: 't2'31 t91:
6. North Anna 1 Steam Generator Repair.

Confirms steam generator repair project can be conducted under 1 O CFR 50.59.

Target date: 11/30/91.

7. TS2~ 8 !Revmse~ Sett~emernt fM@n~i@rBrn~.

Significantly reduces number of survey points requiring periodic survey.

Target date:

~ 0/81/91. 2/15/'IZ

8. TS231 Control Room Habitability. Adds automatic switchover of ventilation on appropriate RM signal and clarifies ventilation trains.

Target date: 10/31/91-. 12/30/'II

9. TS263 RTD Bypass. Supports scheduled modification to serve the RTD bypass manifold which impacts RPS response times. Target date:

-10/31 /91. /2/30/91 18 1 O. UFSAR Revision No.;J,r. Continued improvement and upgrade of the UFSAR. Target date: --9/30/91. ltj3o/9' I S~il~@we~ at the N RC Bold at Virginia Power Date: t.laA-9/t;z/91 Approved: ~J *:.:..A:.:. *..::S:.:.:ta::.l.:._I ___ _

M.L. Bowling

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Septempber 19, 1991 LONG STANDING LICENSING, OPERATING EXPERIENCE ISSUES Control Room Design Review Modification for Surry PSARV Piping Supports and Code Safety Valve Setpoint Drift R. G. 1.97 full compliance review and resolution of known non-compliance Control Room Habitability T.S. change for North Anna Vital Area definition for North Anna SOER 84-7 SOER 84-01 SOER 81-08 SOER 83-09 Section XI Permanent instrumentation modifications for Surry Surry Chiller Upgrade North Anna commitments made based on implementing-MERITS

. SOLUTION TO MACROFOULING IN THE SERVICE WATER SYSTEM.

SURRY POWER STATION CONCERNS

1. FOULING OF SAFETY-RELATED EQUIPMENT.
2. LOSS OF GENERATION CAPACITY.

IMMEDIATE ACTIONS START SAMPLING SERV.ICE WATER (SW) AND TRENDING THE RESULTS."

ALTERNATELY STAGNATE THE 48" HEADERS TO REDUCE 02 AND FOOD TRANSPORT.

INJECT CHLORINE IN THE STAGNATE 48" HEADER.

RESULTS OF IMMEDIATE ACTIONS 5 POINTS ARE BEING SAMPLED IN THE SW SYSTEM FOR 7 VARIABLES.

2 MONITORING INSTRUMENTS ARE CURRENTLY DEPLOYED (INTAKE CANAL AND LOW LEVEL).

ALTERNATE STAGNATION AND CHEMICAL INJECTION HAVE SIGNIFICANTLY REDUCED FOULING IN THE BC HEAT EXCHANGERS.

BOROSCOPE AND DIVER INSPECTIONS OF THE 48" (A&C) HEADERS HAVE SHOWN NO SIGNIFICANT GROWTH IN THE HEADER. TREATMENT AND STAGNATION HAS BEEN EFFECTIVE.

ACTIONS IN PROGRESS VIRGINIA INSTITUTE OF MARINE SCIENCES (VIMS) IS CONDUCTING A STUDY, ECOLOGICAL SURVEY, AND LABORATORY EXPERIMENTS ON MACROFOULING AGENTS IN SW.

THIS INCLUDES:

1. LITERATURE SEARCH OF ALL ORGANISMS ENCOUNTERED FOR LIFE HISTORY,.TOLERANCES TO ENVIRONMENTAL VARIABLES, REPRODUCTIVE PERIODS, CURRENT/RECOMMENDED CONTROL METHODS, AND TOXICOLOGICAL STUDIES.
2. ONE YEAR STUDY OF THE COLONIZATION AND MACROFOULING AGENTS IN THE SW INTAKE CANAL. THIS INCLUDES REACTION OF ORGANISMS TO ENVIRONMENTAL CHANGES AND THE 7 MONITORED VARIABLES (02, SALINITY, TEMPERATURE, pH, AMMONIA, CONDUCTIVITY, AND CHLORINE [AS APPLICABLE]).

REACTIONS TO THESE VARIABLES ARE CONSIDERED TO BE USED AS AN EARLY WARNING SYSTEM FOR VIRGINIA POWER AND AS VARIABLES WHICH MIGHT CONTROL GROWTH.

I

ACTIONS IN PROGRESS (CONT'D)

3.

CONDUCT FLOW TESTS ON HYDROIDS IN THE LABORATORY AS WELL AS CHLORINE AND AMMONIUM BIOASSAYS. (TEMPERATURE THRESHOLD AND SODIUM BROMIDE HAVE SINCE BEEN AD~ED.)

COUPONS WERE DEPLOYED IN THE INTAKE CANAL TO MONITOR/STUDY GROWTH AND TO TRY VARIOUS MACROFOULING CONTROL COATINGS.

1.

10 COATINGS ARE BEING STUDIED (WOOLSEY RED, WOOLSEY BLUE, INTERLUX BLUE, COAL TAR EPOXY, COPPERCLAD, EPCO-TEK 2000, BARNACLE X, BIOCLEAN, CHESTERTON, AND BELZONA).

2.

TO-DATE THE WOOLSEY RED AND EPCOTEK 2000 ARE EFFECTIVE AND THE COAL TAR EPOXY PROLIFERATES GROWTH (THIS INFORMATION IS PRELIMINARY).

FILTER SAMPLING OF THE INTAKE CANAL AND THE BACK OF THE TRAVELLING SCREENS IS BEING CONDUCTED TO ASSESS THE EFFECTIVENESS OF THE SCREENS.

ACTIONS IN PROGRESS*

(CONT'D)

A MACROFOULING CONSULTANT IS STUDYING THE VIMS DATA IN ORDER TO MAKE ENGINEERING RECOMMENDATIONS FOR SW HARDWARE CHANGES. THE FOLLOWING TECHNIQUES ARE BEING CONSIDERED:

1.

IMPROVED TRAVELLING SCREEN DESIGN

2.

INSTALLED FILTERS

3.

NON-TOXIC FOUL RELEASE COATINGS

4.

TOXIC COATINGS

5.

HEAT TREATMENT

6.

FRESH WATER INJECTION

7.

ROBOTICS

8.

ACOUSTICS/ULTRASONICS

9.

CHEMICAL INJECTION

10.

ELECTRICITY

11.

ULTRAVIOLET

SCHEDULE VIMS' ECOLOGICAL REPORT DUE APRIL, 1992.

STONE & WEBSTER REPORT ON HARDWARE MODIFICATIONS DUE JUNE, 1992.

RECOMMENDATIONS WILL BE PROVIDED AS THEY BECOME AVAILABLE.

DEVELOP DESIGN CHANGE PACKAGE FOR HARDWARE CHANGES TARGETED FOR 1993 IMPLEMENTATION.

STUDY RECOMMENDATIONS CURRENTLY IN PROGRESS CHEMICAL TREATMENT, STAGNATION OF 48" SW HEADERS & WET LAYUP REPAIR OF LOW LEVEL AND HIGH LEVEL SCREENS AND SCREEN WASH SYSTEMS HYDROID GROWTH REMOVAL AT LOW LEVEL EEL POTS HAVE BEEN PURCHASED AND DEPLOYED IN THE INTAKE CANAL RECOMMEND USE OF CHESTERTON IN LIEU OF COAL TAR

NORTH ANNA SERVICE WATER SYSTEM MODIFICATION HISTORY THE NORTH ANNA SERVICE WATER SYSTEM HAS A HISTORY OF MICROBIOLOGICALLY INDUCED CORROSIQN (MIC) ATTACK CAUSED BY SULFATE REDUCING BACTERIA (SRB).

YEAR 1983/84 1984 1987 1987 1988 1989 ACTIVITY REPLACED 3" & 4" LINES TO/FROM CHARGING PUMP COOLERS WITH STAINLESS STEEL INSTALLED TEMPORARY CHEMICAL ADDITION SYSTEM INSTALLED NEW RESERVOIR SPRAY SYSTEM PERFORMED MECHANICAL CLEANING PERFORMED CHEMICAL CLEANING REPLACED 4" UNIT 1 CONTROL ROOM CHILLER PIPING

YEAR 1990/1991 1990 1991 1991 NORTH ANNA SERVICE WATER SYSTEM MODIFICATION HISTORY (~ONT'D)

ACTIVITY REPLACED 3" LINES TO CONTAINMENT PENETRATION COOLERS, SWITCHED FROM SERVICE WATER TO CC COMPLETED CHEMICAL ADDITION SYSTEM INSTALLED CATHODIC PROTECTION ON 36" BU RIED PIPING BEGAN DESIGN TO REPLACE LEAKING 4" U2 CHILLER PIPING

  • .;~

NORTH ANNA SERVICE WATER SYSTEM ACTION PLAN COMPLETE CONCEPTUAL ENGINEERING STUDY PERFORM INSPECTIONS/MONITOR CORROSION RATE INOCULATE SYSTEM TO ARREST MIC REPLACE EXISTING SUSPECTED LEAKING PIPING (UNIT 2 CONTROL ROOM CHILLER PIPING)

PERFORM RISK ASSESSMENT/LICENSING ACTIVITIES (WILL SUBMIT FOR NRC APPROVAL 3RD QUARTER 1992)

NORTH ANNA SERVICE WATER SYSTEM ACTION PLAN (CONT'D)

PREPARE DCP'S FOR PRIORITY REPAIRS/REPLACEMENT UNIT 1 RSHX PIPING BY-PASS/REPAIR UNIT 2 RSHX PIPING BY-PASS AUXILIARY SERVICE WATER PIPING BY-PASS/REPAIR CC HX PIPING, CLEANING, & COATING SERVICE WATER PUMP UPGRADE PREPARE DCP'S FOR OTHER MODIFICATIONS REPLACE EXPOSED PIPING LINE SW RESERVOIR SW SYSTEM CLEANUP RE-COAT 36" LINES

PROTECTED AREA SECURITY FENCE

. SERVICE BUILDING~_ -----\\-11_.

36* BURI ED SW LINES

\\..

LAKE ANNA INTAKE STRUCTURE TURBINE BUILDING 24*. SW LINES TOi X

z4* SW LINES SW TIE-IN VAULT TO COil SW VALVE HOUSE SW Pllll HOUSE I

t**

. 1 11

= 200 f.t..

PROJECT BACKGROUND PRESSURIZER SAFETY AND RELIEF VALVE MODIFICATIONS

  • SURRY POWER STATION INITIAL PROJECT DIRECTION WAS TO MAINTAIN VALVE WATER SEAL DUE TO THE CONCERN OFSTEAM UNDERCUTTING ON THE VALVE SEATS.

UPGRADED PSV SUPPORTS [I.E. PRZR "BELLY BANDS"]

UPGRADED PRZR INSULATION UP TO PSV [I.E. "OVENS'!

TO LESSEN PSV DISCHARGE LOADS]

THIRTEEN (13) NEW SUPPORTS [PER UNIT] WOULD BE REQUIRED ON THE PSV/PORV DISCHARGE LINE DUE TO THE WATER SLUG. CURRENTLY, THERE ARE 29 SUPPORTS ON THE LINE.

TWO OUTAGE IMPLEMENTATION SCHEDULE WAS PLANNED FOR PSV/PORV DISCHARGE LINE.

SUPPORT UPGRADE.

PRESSURIZER SAFETY AND RELIEF VALVE MODIFICATIONS SURRY POWER STATION (CONT'D)

ABOUT SEPTEMBER 1989, THE SETPOINT DRIFT ISSUE EMERGED. SUBSEQUENTLY, VIRGINIA POWER DEFERRED SUPPORT INSTALLATION UNTIL THE ISSUE IS RESOLVED.

WCAP-12910 ISSUED ON 03/31/91 SHOWS VIRGINIA POWER PLANTS WITHIN SAFE OPERATING LIMITS, HOWEVER, MARGIN IS EXTREMELY SMALL WITH THE WATER SLUG.

IMPROVEMENTS IN THE.OPERATING MARGIN CAN BE REALIZED BY GOING TO A STEAM SEAL.

PRESSURIZER SAFETY AND RELIEF VALVE MODIFICATIONS SURRY POWER STATION (CONT'D)

ENGINEERING EVALUATION TO DELETE WATER LOOP SEALS UPSTREAM PIPING OF THE PSV AND PORV WILL REQUIRE A DRAIN LINE.

PSV TRIM MUST BE UPGRADED FOR STEAM.

ROUTING OF PSV/PORV LOOP SEAL DRAINS IS FEASIBLE.

NO OPERATIONAL PROBLEMS ARE EXPECTED WITH PSV'S/PORV'S ON STEAM BASED ON OTHER PLANT'S AND INDUSTRY EXPERIENCE.

EXISTING PSV/PORV DISCHARGE LINE SUPPORTS ARE EXPECTED TO BE SATISFACTORY AS IS! NO DISCHARGE LINE SUPPORT WORK IS ANTICIPATED.

\\l,.

  • PRESSURIZER SAFETY AND RELIEF VALVE MODIFICATIONS SURRY POWER STATION (CONT'D)

CURRENT PROJECT DIRECTION INSTALL PSV AND PORV DRAINS UPGRADE PSV TRIM FOR STEAM COMPLETE PSV/PORV DISCHARGE PIPE LOAD ANALYSIS FOR STEAM LOADS TWO OUTAGE IMPLEMENTATION SCHEDULE FIRST OUTAGE->. VERIFY DRAIN LINE/SUPPORT LOCATION (U1-92/U2-93)

SECOND OUTAGE-> INSTALL DRAIN LINE AND VALVE TRIM (U1, U2-94)

  • Auxiliary Spray from Charging Pump,--

LoopC Cold Leg

._ __ nc 131 Loop A Cold Leg

---...---...---------------..----* To Pressurizer Relief Tank LqopC Ho~Lag PRESSURIZER DIAGRAM SOV SUV RC*

nc-1ou,-1 IOIA-2 SOY SOV RC*IOIB*I RC-1018-2 I

I Refueling Cavily

To PRT 12" -

RC -

36 (New) 1*-Rc-??

1*-RC-25 (E,cl9tlng)

PSV Loop Seal Drain Line

~PSV 47" floor *l*v (New)

Pzr Liquid Sampl*

(E,cl11tlng)

To Sample System To --.--<<*---I LT Pzr Liquid Sampl*

(New) 18" floor elev

~PSV

~PSV 6"' -

RC -

62 Block Valve*

PORV*

r---'"'-;;...;._"'----' PORV. Loop S*ol Upper Level Top11 (3)

PRESSURIZER 1-RC-E-2 Lower Level Tops (3) 1----'

Drain Lin*

Cond*n9at*.Pot To L*vnl Tron11mltters (LT)*

1459. 1460. 1461. 1462 SURRY 1&2 PSV/PORV C

  • -a

)>

~

LOOP SEAL DRAIN SCHEMA TIC (Not to scale)

JEK B/12/91

PRESSURIZER SAFETY AND RELIEF VALVES NORTH ANNA ALL UNIT 2 MODIFICATIONS ARE COMPLETE AND UNIT 2 IS IN COMPLIANCE WITH NUREG 0737 IID1.

UNIT 1 MODIFICATIONS ARE COMPLETE EXCEPT FOR THE FINAL PHASE OF THE DISCHARGE PIPING HANGER MODIFICATIONS.

ACCESSIBLE BASE PLATES-COMPLETE SOME HIGHER CAPACITY HANGERS INSTALLED REMAINING WORK INCLUDES APPROXIMATEL V 20 HANGERS TO BE REMOVED, NEW HANGERS INSTALLED IN NEW LOCATIONS REMAINING SCOPE OF UNIT 1 WORK IS SCHEDULED FOR 1993 UNIT 1 REFUELING OUTAGE.

SCOPE MAY BE REDUCED BASED ON IMPACT OF LOOP SEAL DRAINS.

INSTALL UNIT 2 LOOP SEAL DRAINS IN FALL 1993 OUTAGEe INSTALL UNIT 1 LOOP SEAL DRAINS IN FALL 1994 OUTAGE.

CONTROL ROOM DESIGN REVIEW SURRY AND NORTH ANNA POWER STATION CRDR RESULTS WERE INITIALLY FORWARDED AS PART OF A FINAL

SUMMARY

REPORT IN 1986 (ATIACHED ARE ANNOTATED

SUMMARY

TABLES FROM THESE SUBMITIALS)

IN THE REPORT FOUR CATEGORIES OF CORRECTIVE ACTIONS WERE IDENTIFIED WITH IMPLEMENTATION DATES AS FOLLOWS:

IMMEDIATE - WITHIN 2 YRS SHORT TERM - WITHIN 4 YRS

  • LONG TERM - WITHIN 8 YRS NORMAL PROGRAM -AS OPPORTUNITIES ARISE ASSOCIATED WITH REPLACEMENTS OR MODIFICATIONS NOTE: CORRECTIVE ACTIONS GROUPED COMMON HED'S PROGRESS TO DATE IS ANNOTATED ON THE ATIACHED

SUMMARY

TABLES.

SURRY HAS DEFERRED A NUMBER OF SHORT TERM CORRECTIVE ACTIONS DUE TO HIGHER PRIORITIES DURING THE PERIOD 1989-1991 NORTH ANNA IS ON SCHEDULE

CONTROL ROOM DESIGN REVIEW (CONT'D)

WE ARE CURRENTLY REASSESSING THE NEED FOR THE REMAINING CORRECTIVE ACTIONS. VIRGINIA POWER ENGINEERING, OPERATIONS, TRAINING AND HUMAN FACTORS PERSONNEL WILL CONDUCT THE REASSESSMENT BASED ON INPUT FROM THE FOLLOWING FACTORS AND PERSONNEL:

ORIGINAL HUMAN FACTORS EVALUATIONS OPERATIONS EXPERIENCE SIMULATOR TRAINING PERFORMANCE RESULTS OF OUR REASSESSMENT.WILL BE PROVIDED BY JUNE, 1992.

REMAINING CORRECTIVE ACTIONS WILL BE COMPLETED BY THE END OF 1994 CONSISTENT WITH THE ORIGINAL LONG TERM SCHEDULE

PROPOSED CORRECTIVE ACTION RESPONSIBILITY

[NGJNHRING STUDIES AND,.

DESIGN CHANGES NON-DESIGN CHANGES (OPERATIONS)

TRAINING TOTAL NUMBER COMPLETED

_)

TABLE FSR-1 CONTROL ROOH DESIGN REVIEWS FINAL SDlltARY REPORT NORTH ANNAPOIH'.R STAT ION UN ITS 1 AND 2 SUtitARY OF PROPOSED CORRECTIVE ACTIONS AND IMPLEMENTATION SOIEDULE I (0-2 yrs) 18 13 3

34 34 PROPOSED IMPLEMENTATION SCHEDULE ST (0-4 yrs)

LT (0-8 yrs) 34 2

0 36 36 2

0 0

2 0

ATTACHMENT 1 TABLE FSR-1 SERIAL NO. 85-268C SUBMITTED JUNE 30,1986 NP 10 9

0 19 13 No 2

0 0

2 2

1 The total number of Corrective Actions per the listing is 80.

The total number of Corrective Actions listed in this Sunmary is 93.

The additional 13 in the Sunmary represents the implementation of the study reconmendations.

flP.

7 of 20

.Total 66 24 3

93 85

PROPOSED CORRECTIVE ACTION RESPONSIBILITY I

ENGINEERING DESIGN CHANGE

& STUDIES NON-DESIGN CHANGE (OPERATIONS)

TRAINING TOTAL NUMBER COMPLETED TABLE FSR-1 CONTROL ROd4 DESIGN REVIEWS FINAL SlllWIY REPORT SURRY POWER STATtoN ONITS 1 AND 2 SlllWtY OF PROP0Sffl CoRRECTIVE ACTloNs MD IMPl.EJDTATloN SCIIEDIJ[E PROPOSED IMPLEMENTATION SCHEDULE (0-2 yrs)

SI (0-4 yrs)

LT (0-8 yrsJ 16 30

  • 3 11 2

7 34 32 3

34 8

0 I

ATTACHMENT 1 TABLE FSR-1 SERIAL NO. 06*-171 REVISED PER LETTER NO.89-743, dated 12/14/89 Nt' No 14 3

1 15 3

5 3

Total

  • 66 14 7

87 50

,.,,..... 1'0/21/91 Level I - Nuclear Project Report All Projects

~. ?:,,w~\\-"1 ~ U:i*c-r~ M\\.:1 i0_\\*ztj, EWH APP co DE START. DATE DOE DATE STATUS (222-03) Review the 12-hr WLS 2

G 07/18/91 11/30/91 20%

Shift Assessment and Identify Appropriate Modifications for Implementation (360-02) Implement Action Plan WLS 4 c 03/11/91 07/30/92 30%

to Improve Performance of Sta-tion Planning (544-01) Complete Phase 2 of WLS 3

C 07/22/91 10/30/91**

10%

Development of a Nuclear Mas-ter Plan (629) Conduct Executive commu-WLS 5

G 07/18/91 11/30/91 15%

nication Meetings with All Maintenance Supervision (644) Develop WLS Nuclear WLS 6

E 08/13/91 10/11/91 90%

Update for October BOD Meeting 1 -

I 10/21/91 Level I - Nuclear Project Report All Projects RFS APP co DE START DATE (405-0SA) Maint Work Control WLS 4

C 11/13/90.

Process - Implement Accepted Improvement Items (405-09) Maint. Backlog Mani-WLS 6

C 10/09/90 toring Data - Monthly Status (645) Develop and Implement WLS 1

C 09/10/91 Actions Required to Correct CW Fouling Issues at Surry (646) ~onduct needs assessment WLS 2

C 08/12/91 and benefit analysis of dredg-ing entrance to Surry Low Level Intake Structure 2 -

DUE. DATE STATUS 11/30/91 10%

10/30/91 11/30/91 40%

10/31/91 75%

1*0121)91 Level I - Nuclear Project J Report All Projects MRK APP co DE START DATE (121-01) Surry Station Level I EWH 6

E 11/30/89 Report - Monthly Status (324-02) SPS -

CTS SOER Close-EWH 4

B 09/05/91 out Complete for 1992 Items

{554) SPS INFO Eval -

Complete EWH 6

B* 03/08/91 1991 Commitments - Monthly Status

{635) Develop a Level II Plan EWH 3

C 08/13/91 to review the CNS Rpt on the SPS Unlatched Cntl Rod Event and Implement appropriate cor-rective actions to prevent reoccurrence at SPS 3 -

DOE DATE STATUS 11/14/91 07/01/92 11/14/91 50%

10/30/91 99%

Level I - Nuclear Project Report All Projects GEK APP co DE START DATE (122-01) N. Anna Station Level EWH 6

E 11/30/89 I Report - Monthly Status (630) NAPS INPO Eval -

Com-EWH 6

B 07/18/91.

plete 1991 Commitments-.

Monthly Status (636) Develop a Level II Plan EWH 3

C 08/13/91 to review the CNS Rpt on the SPS Unlatched Cntl Rod Event and Implement appropriate cor~

rective actions to prevent occurrence at NAPS (643) NAPS -

CTS SOER Closeout EWH 4

B 09/05/91 Complete for 1992 Items 4 -

DUE DATE STATUS 11/14/91 11/14/91 10/30/91 99%

12/31/92

  • 10/2i/91 Level I - Nuclear Project Report,

All Projects FKM APP CO DE

~TART DATE DOE DATE STATUS (100-01) Status EWR Backlog -

WLS 6

'E 12/04/89

.Monthly (101-01) Status Engr. Poten-WLS 6

E 12/04/89 tial Problem Reports - Monthly (231-01) Implement Adequacy WLS 6

E' 02/01/90 and Effectiveness Review of Programmatic Changes - Monthly status

-(240-04) Complete Implementa-WI.S

4. C 10/14/91 tion of Procedures for Emerg-ing Engineering Programs (570-02) Conduct a Study of WLS 2

C 10/03/91 Flow Balance and Operating Alignment of NAPS Component Cooling and recommend appro-

. priate modifications to improve efficiency 5 -

11/14/91 11/14/~l 11/14/91 09/01/92

.. 1,0/21/91 Level I - Nuclear Project Report All Projects DLB APP co DE START DATE (012) Configuratioh Mgmt /

FKM 4

D 03/14/89 Design Basis Document (012-lBA) Complete draft FKM 4

D 07/24/90 SDBD's for SPS-RPS, SPS-RH, sps...:Nc, NAPS-RPS, NAPS-NC (012-19) Complete Draft SDBD's FKM 4

D 07/24/90 for SPS-NIS, NAPS-NIS, NAPS-RC, NAPS-CH (012-19A) Complete Draft FKM 4

.D 07/24/91 SDBD's for SPS-RC, SPS-CH (012.;.26) Complete Walkdowns of FKM 4

D 04/01/91 Components At Surry - cumula-tive 72,233 thru 4th Qtr (012-27) Complete Walkdowns of FKM 4

D 0_4/01/91 Components at North Anna -

Cumulative 85,660 thru 4th Qtr (012-29) Complete Upgrade of FKM 4

D 01/15/91 250 Vendor Manuals at Surry -

Due date extended from 9/30/91 (012-30) Complete Upgrade of FKM 4

D _ 01/15/91 250 Vendor Manuals at North Anna - Due date extended from 9/30/91 (012-32) Complete.Relabelling FKM 4

D.10/01/91 of 8,700 Components at SPS (012-33) Complete Relabelling FKM 4

D 10/01/91 of 4,500 Components at NAPS (200-02G) Issue 7th "Exec.

FKM 2

C 09/05/91 Summary" Significant Industry

EWH 1

C 11/22/89 SPS & NAPS (395) Perform review of Surry FKM 4

A 06/19/90 T.S. vs. Surveillance tests (427) Implement NAPS SBO Modi~

FKM 1

A 12/04/90 fications

- DOE DATE STATUS 01/31/92.

  • 10/15/91 90%
  • 12/31/91 50%

01/31/92 40%

12/31/91 12/31/91 12/31/91 50%

12/31/91 50%

01/31/92 20%

01/31/92 20%

11/30/91 5%

11/30/93 15%

12/31/91 55%

11/30/94 5%

lQ/21/,91 Level I - Nuclear Project Report All Projects DLB APP CO DE* START DATE DOE DATE STATUS (464-03) Complete SPS SW Type 2 study - Due date extended from 2-1-92 (473) Implement SPS SBC Modi-fications (473-02) SPS SBC - Complete Type 2 FKM 2

A 05/02/91 FKM 1

A 12/04/90 FKM 2

A 12/04/90 (507) Complete Type 2 study FKM 2

C 01/10/91 for NAPS Service Water system pres~rvation (536-02) Expand PMT Program to EWH 4

A 05/02/91 key non-safety related compo-nents at Surry (576) Evaluate feasibility of FKM 2

C *05/02/91 abandoning SPS discharge vac-uum priming (577) Obtain SNSOC approval of FKM 1

D. 05/02/91 PS chiller DCP (578) Obtain SNSOC approval of.FKM 1

D 05/02/91 SPS cc thermal barrier DCP (580) Obtain SNSOC approval of FKM 1

C 05/02/91 NAPS Gland Steam Piping

.Replacement (597) Complete modifications EWH 1

D 06/25/91 to the SPS WGDT hydrogen ana-lyzer system - Due date extended from 8/9/91 (637) Consolidate Generic Post-Mod Test Proc.

{638) Complete GL 89-13 Ser-vice Water Req.

(638-01) complete NAPS Base-

.line Testing (638-02)- Flow Test SPS #1 RSHXs (638-03) Complete Follow-up Actions FKM 4

C 08/13/91 FKM 1

A 08/13/91 FKM 2 A 08/13/91 FKM 2

A.08/13/91 FKM 4

A 08/13/91 7 -

06/01/92 11/30/94 12/02/91 15%

5%.

70%

11/20/91**

70%

03/01/92

  • 15%

01/15/92 20%

11/01/91.

50%

11/15/91 12/05/91 10/31/91 12/31/91 05/19/92 12/13/91

  • os/19/92 01/30/92 90%

70%

97%

50%

10%

1,0/21/,91 Level I - Nuclear Project Report All Projects

  • DLB APP CO DE START DATE DOE DATE STATUS (657) Complete Reassessment of FKM 4

D 09/24/91 SPS CRDR Commitments 8 -

06/15/92 5%

10/21/91.

Level I - Nuclear Project Report

/

All Projects.

. GHF APP CO DE

  • START DATE DUB DATE STATUS (076-05) Develop software FKM 4

C 04/02/91 revisions for,tnstrument Uncertainty Calculation Pro-gram (168-02) Fault current Int Cap FKM 2

D 10/18/89 (NAPS) - Prepare Type 1 Report (271-05)-Complete Pilot EQ QDR FKM 4

A 10/17/91 Revision Project (280-04) R.G*. 1.97 -

Complete FKM 2

A 09/05/91 Review of Phase 5, 6, & 7

  • Variables (328-06) Prepare annual update FKM 6

A 06/27 /91 of Appendix R Reports for SPS.

& NAPS (363-03) Provide Long Term Recommendations for Improve-ments to T/G Voltage Regu-lators (394-03) Support SPS.EDSFI Audit RFS 2

D 10/17/91 FKM 2

A 10/17/91 12/31/91 10/31/91 01/31/92 12/01/91 12/01/91 03/01/92 11/30/92 80%

40%

(467-02) Impleme.ntation of~

FKM l

D 04/02/91.

  • 12/06/91 89%

PARS for control of PLC logic and digital control devices (479-04) Provide Engineering

,EWH 4

A 10/17/91 12/15/93 Support to SPS for Inspection of Fire Barrier Penetration Seals (537-01) Develop Station Seal-FKM 4

C 05/~9/91 12/31/91 5%

ing Document 9 -

10/21/91 Level I - Nuclear Project Report All Projects RMB APP co DE START DATE (068-07) complete draft North

  • FKM 6

A 07/16/91 Anna IPE Report 1

(510-02) SPS 1 Rx Vessel PrO-FKM 1

D 02/06/91

  • gram - Complete Fabrication of Flux Suppression Inserts (511) *Complete Multi-loop FKM 2

D 01/14/91 Feedwater Malfunction Analyses for SPS and NAPS (624) Develop Level II Plan to EWH 3

H 07/16/91 Implement Reactivity Mgmt Rec;..

ommendations (625) Complete North Anna 1 RFS 2

H 07/16/91 extended SG Tube Plugging Analysis (655) Complete NAC Cask Tip-FKM 2

H 09/15/91 Over Analysis and Licensing Pac){age 10 -

DUE DATE STATUS

  • 02/28/92 40%

03/31/92 10%

12/31/91 85%

10/10/91 99%.

01/15/92 45%

11/15/91 25%

--~

~0/21/91 Level I - Nuclear Project Report All Projects ESG APP co DE START DATE DUE DATE STATUS (095) Complete ISI Prgm FKM 4

A 05/11/89 10/17/91 Enhancements - Monthly Status (623) Develop a Corrosion Mon-FKM 4

C 07/17/91 10/31/91 65%

itoring Program for Surry Aux-iliary systems (633-01) Complete Identifica-FKM 4

A 09/23/91 12/31/91 10%

tion of Lines which may con-tain Longitudinal Welds (654) Monitor developments in RFS 2

A 09/23/9'1 11/30/91

  • Trojan Eddy Current and S/G Tube Analysis and report sig-niflcant developments
  • ( 658) Develop Level II Plan.

FKM 2

C 10/04/91 11/29/91 40%

for recommending a strategy for NAPS Unit 2 steam Genera-tors 11 -

10/21/91 Level I - Nuclear Project Report All Projects CMR APP co DE START DATE (021-04) SPS Admin Bldg -

FKM 1

G 12/04/90 Occupy Facility (106) N. Anna Long Term Roof EWH 1

D 05/30/89 Repairs (1991" Prqgram)* -

Due date extended from 10/14/91 (259-03) PSVIS - Issue final EWH 2

D 06/06/91 draft DCP -

SPS #1 (317) Erosion/Corrosion -

EWH 2

A 01/16/90 Develop Layup Methodology and Issue Report -

Due date extended from 2/28/91 (392-01) Service Water Sys -

FKM 2

A 02/06/91 Prepare Tech Report on GL 89-13 tests and associated calculations (440-02) Perform data review FKM 2

C 07/05/91 to reduce scope of Secondary Insp Prgm (533-01) Piping Line Lists -

FKM 2

D 02/25/91 Establish criteria for Calcu-lating Sys Design Parameters (599) Document Surry cc Con-FKM 6

A 07/05/91 tainment Issues in Tech Report 12 -

DUE DATE STATUS 02/01/92 80%

11/29/91 99%

12/02/91 35%

11/18/91 82%

10/30/91 87%

12/31/91 18%

12/31/91 62%

11/15/91 30%

10/21/91 Level I - Nuclear Project Report All Projects MWG APP co DE START DATE (614) North Anna #1 S/G FKM 1

C 07/09/91 Replaceinent (614-05) Fabricate & Delive~

FKM 1

C 10/27/89 S/G Lower Shell Assemblies to North Anna (614-06) Complete Contract FKM 2

f 08/19/9i, Negotiations for SGR Phase II.

13 -

DOE DATE STATUS 12/31/93 14%

08/01/92 70%

05/01/92

  • 20%

10/21/91 Level I - Nuclear Project.

JPO (571-02) Identify All Appro-priate Perf Indicators for 1992 Nuclear Business Plan Report All Projects APP co DE WLS

  • 3 C

(571-03) Update 1992 NBP Based WLS 3

C on approved Budget and Goals

. (Final Text)

(639) Develop JTR INPO Speech WLS 6

E

- Practical Strategies f6r Achieving Peak Plant Perform-ance (644) Develop WLS Nuclear WLS 6

E Update for October BOD Meeting

.(659) Develop Nuclear Update WLS 6

E for WLS to brief NRC Chairman Selin

-. 14 -

START DATE 08/01/91 08/13/91 08/13/91 08/13/91 10/08/91 DUE DATE STATUS 12/06/9l 5%

12/31/91 5%

10/23/91 40%

10/11/91 90%

11/01/91

10/21/'91.

Level I -

Nuclear Pro-ject Report Al*l Projects MLB APP CO DE START DATE DOE DATE STATUS

. (005-05) !~sue Monthly Mgmt.

JPO 6

B 02/28/91 Report addressing IOER problem resolution effectiveness (365-02) Implement 1991 OE Assessment Plan JPO 4

C 01/01/91 (375-01) MERITS - Obtain NRC JPO 4

A 03/14/90 Approval of T.S. Change for North Anna - Due.date extended*

from 11/16/90 (375-02) MERITS - Obtain NRC JPO 4

A 01/01/91 approval of T.S. Change for Surry (480) Implement Corp.Windows JPO 4

E 01/01/91 (482) Implement North Anna SALP Preparation Action P.lan (483) Implement 1991 CNS Assessment Plan EWH 4

A 01/01/91 JPO 4

  • C 01/01/91 (484-01) Reduce UFSAR backlog JPO 4

C 07/01/91 (541) Develop Licensing Top jpo 6

A 01/22/91 "10" Priority List and Period-ically Update - Monthly status (555) Develop Policy for PLEX JPO 2

C 03/01/91 (556) Develop and.Implement JPO 4

A 03/01/91 Integrated SA/QV Program (558-01) Implement Surry SALP EWH 4

A 07/01/91 Improvement Action Plan (601-01) Provide Qrtly Update JPO 4

H 09/26/91 of Long Standing Licensing &

Operating Experience Issues (632) Complete review of SOER JPO 6

B 08/01/91 91-01 (control of evolutions during Special Tests) and pro-vide written response of actions taken to INPO (647) Develop and Implement a JPO 6

E 09/11/91 Quarterly DR Trend Report 15 -

10/31/91 12/31/91 06/30/93 12/31/92 10/31/91 10/31/91 12/3-1/91 70%

74%

40%

80%

70%

12/31/91 40%

10/31/91 12/31/91 30%

10/31/9i 75%

,03/31/92 40%

12/31/91 11/01/91 70%

10/30/91 60%

10/21/91 Level I - Nuclear Project Report All Projects WWW APP co DE START DATE DUE DATE STATUS (014-10) Sta Proc. Upgrade -

JPO 4

A 10/01/91 12/31/91 I

Complete 4th Qtr Schedule (015-05) Breakers -

Conduct EWH 2-A 07/01/91 12/31/91 5%

Biannual Program Review (016-09) Check Valves -

Annual RFS 2

c* 09/24/91 09/30/92 Program Assessment (017-07) MOV - Evaluate Impact JPO 1

C 09/19/91 10/31/91 60%

of MOVATS study (020-06) Provide 6 month EWH 6

C 05/01/91 11/03/91 10%

updates on RCS Filtration Perf Results (056-02} Report on Assessment JPO 2

H 12/15/89 12/31/91 30%

of New Protective Clothing Performance -

Due Date Extended from 12/31/90 (388-02) SPS TVFT -

Submit RFS 2

C 08/22/91 12/31/91 20%

Notification to NRC

.(398-02} EOP Key/Lock Control EWH 4

A 02/01/91 04/01/92 80%

Implement OPAP-008 (Admin control of valves, locks and -

switches) -

Due date extended from 6/30/91

( 405-11) Upgrade PM Program -

JPO 4

C 05/17/91 12/31/91 70%

Complete 3 Systems (Cumulative 6 Systems}

(451) Develop Program to Man-EWH 4

C 10/09/90 12/06/91

-. age Scaffolding -

Long Term

-Recommendations f-

'T (478} Investigate Whole Body JPO 4

C 09/24/91 11/30/91 30%

Count Processing (487-02) Evaluate Implementa-JPO 6

B 08/01/91 11/30/91 30%

tion of INPO Good Practices Relating to Procedures (502-03} Early Boration -

Com-RFS 2

C 08/22/91 12/31/91 75%

plete Evaluation 16 -

10/21/91 Level I - Nuclear Project Report All Projects WWW APP co DE START. DATE DUE DATE STATUS (506) Determine LLRW source RFS 2

A 01/11/91 03/30/92 80%

term characterization partici-pation - Due date extended from 2-28-9lr Due date extended from 4-30-91; Due date extended from 09/30/91 (553) Develop Whole Body Con-RFS 4

B 02/28/91 06/30/92 25%

firmatory Measurement Program

- Due date extended from 6-30-91 to 6-30-92 (567) Report status of 5-Y~

RFS 4

H 08/01/91 10/31/91 60%

ALARA Pian~ 3rd Qtr Status (58~} Evaluate AP Problems at JPO 2

NAPS - Due date extended from C

05/23/91 11/30/91 10/1/91 (585) Conduct Qtrly Mgr Brief-JPO 6

E 08/01/91 10/31/91 ings on CFAR Report (586-01) Implement 10CFR20 JPO *4 A

06/14/91 01/01/93 20%

Rule (642) Discontinue RP Indoctri-JPO 4

H 08/26/91 01/01/92 30%

nation-for non-RCA Users (650) Develop PM Program for RFS 1

C 09/19/91 12/18/91 30%

cw Intake System (651) Implement "Chemistry JPO 4

G 09/19/91 12/31/91 50%

Inquiry" Recommendations (652) Update LLRW Contingency RFS 6

H 09/24/91 12/30/91 Plan (660) Assess effectiveness of JPO 2

H 10/08/91 11/05/91 Safety Glasses and Hearing Protection policies and recom-mend modifications as appro-

.priate 17 -

10/21/91.

Level I - Nuclear Project Report All Projects TMW APP co DE START DATE DUE DATE STATUS (456) Complete Admin Controls JPO 4

G 10/15/90 12/31/91 35%

Upgrade Prgm for Nuclear

  • Training (521) Develop and implement JPO 5

G 01/14/91 12/31/91 75%

Shift Supv Initial Training and Qualification Prgm (592) Prepare Opns Trng Prgms JPO 6

B 06/12/91 10/31/91 90%

Biennial Rpts to INPO (593) Upgrade SPS Simulator

. JPO 4

C 06/12/91 11/15/91 70%

Incore Thermocouple Response (594) Implement Nuc Matls Mgmt JPO 5

G 06/12/91 12/31/91 50%

Trng Program (626) Host NAPS tour by WLS 4

B 07/18/91

. 11/04/91 25%

DOE/Soviet Working Group on Training (628) Host NAPS tours by JPO 4* G 07/18/91

.10/14/91 55%

Southside Electric Cooperative (663) Conduct spouse VIP tour WLS 4

G 10/14/91 11/09/91 at Surry (664) Conduct review of WLS 5

G 10/14/91 12/31/91 requirements for.General Employee Training (665) conduct review of WLS 5

G 10/14/91 10/31/91 requirements for Emergency Preparedness Training 18 -

lQ/21/91 Level I - Nuclear Project Report All Projects FBM

. APP CO DE START DATE DUE DATE STATUS (443-01) Finalize *and imple-JPO 4

C 10/23/90 07/31/92 20%

ment Materials Staging Pro-cess; including systems upgrade at stations - Due date extended from 7/15/91 (461-04) Develop and publish JPO 3

E 07/18/91 10/25/91 60%

Qrtly Rpt on Nuclear group's Surplus Material (462-05) Establish Criticality. JPO 4

C 07/05/91

  • 03/31/92 25%

code for materials allocation from Planning Dept - Due.Date extended from 09/20/91 (527-03) Complete lighting JPO 1

H 02/21/91 11/22/91 75%

improvements in SPS Wrehse and laydown areas (528-02) Place Blanket Orders JPO 4

F 02/26/91

  • 10/04/91 98%

with vendors for Commodity Materials 528-03) Establish Commodity JPO 4

F 07/05/91 12/13/91 75%

aterial B.O. for Fasteners (528-04) Establish Commodity

. JPO 4

F 07/05/91 10/25/91 99%

Material B.O. for_Fittings (581) Reclaim Wrhse A/B for RFS 1

C 05/09/91 03/31/92 5%-

SPS Mtls storage (656) Review Purchase of P-250 JPO 3

F 10/03/91 Spares from Beaver Valley 19 -

l0/2*1/91 Level I - Nuclear Project Report.

All Projects WRW APP CO DB START DATE

  • DUB DATE STATUS (139-04)* Implement Doc. Con-

.JPO 4

C. 11/30/90 trol Program (296-03) Implement action plan JPO 3

F 02/19/91 to maintain Project.Authoriza-tion Resolutions within 60-day limitation (407-08) Report to INPO 3rd JPO 3

F 08/01/91 Qtr Perf Indicators (491-01} Implement Approved JPO 3

F 07/18/91 Budget Process Modifications recommended by the budget task team (538) Complete 1991 Automation JPO 3

C 01/22/91 Plan for Conf. Mgmt Systems (616) Provide status on Con-EWH 6

G 07/09/91 tractors - monthly (617) Complete 1992 Budget JPO 3

F 07/09/91 Process (618) Complete 1992 Goals Pro-JPO 3

c 07/09/91 cess (619) Develop 1992 Business Plan Indicators JPO 3

C 07/09/91 20 -

11/30/91 12/31/91 85%

75%

11/01/91 12/31/91.

70%

12/31/91 11/14/91 12/20/91 12/31/91 01/20/92 70%

60%

10/21/91 Level I - Nuclear*. Proj act Report All Projects JEC APP co DE START DATE DUE DATE STATUS (137-04') Complete draft of JPO 2.ff 08/13/91 10/30/91 80%

Common Virginia Power Emerg Plan

( 448-01). Implement INPO Casu-JPO 4

B 11/07/90

.10/30/91 75%

alty Control Drill Schedule (598) Establish Generic Con-JPO 4

C. 06/25/91 10/30/91 95%

troller org...,. Due date extended from 8/15/91 - Due date extended from 09/30/91 (608-01) Review exercise JPO 3

A* 09/05/91.

10/30/91 85%

schedules against master

.schedule, integrate and approve (609-02) Evaluate and Incorpo-JPO 3

C 09/15/91 12/31/91 40%

. rate Comments on draft EALs_

(610) Status report on State JPO 6

A 07/05/91 10/30/91 EP support activities~

Monthly (611) Submit Scope & Objec-JPO 3

A 07/05/91 10/17/91 99%

tives for 1992 NAPS Graded Exercise (612-01) Develop Information JPO 2

A 09/19/91 10/30/91

. 25%

Transfer Mechanisms for DES during Emergencies (661) Develop a formal inter-JPO 4

H 10/07/91 12/15/91 face between Radiological Emergency Response and Emergency Restoration 21 -

lv/21/91 Level.I -

Nuclear Project Report All Projects LNH APP co DE START DATE DUE DATE STATUS (587-01} Implement improve-WLS 4

C 06/28/91 11/30/91 50%

ments in the QC Contractor Program (604} Follow-up H.P. Methodol-WLS 4

C 08/21/91 10/31/91 75%

ogies - North Anna/Surry (605) Follow-up Operations WLS 4

C 09/11/91*

12/13/91 10%

Methodologies - North Anna/Surry (606} Follow-up Maint Method-WLS 4

C 10/07/91 12/11/91 ologies -

North Anna/Surry (607) Engr Assessment -

Com~

WLS 2

C 11/04/91 12/05/91 puter Software Control (641) Conduct an assessment of EWH 2

G 08/15/91 12/31/91 10%

use of Operator Aids at NAPS and SPS (649) Resolve GNS Dry Cask QA WLS 4

D 09/10/91 11/22/91 Issues

.(666) Review and Revise Esca-WLS 4

C 10/15/91 lation Procedures for Routine DR's submitted by QA 22 -

10/21/91 FWH Level I - Nuclear Project

. Report All Projects APP CO DE START DATE DOE DATE STATUS 23 -

10/21/91

  • Level 1-- Nuclear Project Report All Projects WRR APP co DE START DATE DUE DATE STATUS (236~02A) Maintain Nuclear WLS 5 -G 01/01/91 12/31/91 99%

Staffing at 99% or greater for authorized number -

2320 (564) Prepare for 1992 IBEW WLS 3

G 03/14/91 12/31/91 -

80%

Contract Negotiations (621) Issue Monthly Nuclear WLS 6

G 10/01/91 10/31/91 Newsletter to All Nuclear Employees 24

, 18/21/'91 Level I - Nuclear Project Report All Projects HRJ APP co DE START DATE (177-0lB) NAPS Security EWH 2

A i>l/18/90 Upgrades - Complete Phase I-(DCP-90-02) -

(177-02A) Surry Security EWH 2

A 08/15/90 Upgrades - Complete_Type II Eng:r study*

(177-02B) Surry Security EWH 2

A 09/0~/91

  • Upgrades and Zones - Complete Type II Engineering Study (178-0lB) NAPS Security Zones

- Complete Type II Engr*study EWH 2

A 05/01/91 on Secondary Security Con-trolled Areas (178-02B) Surry Security Zones EWH 2

A 08/15/90

- Complete Type II Engr Study 25 -

DUE DATE STATUS 11/30/91 98%

04/30/92 10%

04/30/92 40%

Number and Percentage of Survey Respondents that have been through the. Fitness For Duty Testing Process:

Innsbrook 220

. 83%

Surry 370 89%

NorthAnna 334 87%

OVERALL 924 87%

"Do* you feel that the Virginia Power Nuclear FFD Program. is successful in promoting a Drug-Free Workplace ?"

Innsbrook 89% Yes 3% No Surry 86% Yes 8% No N orthAnna 86% Yes 9% No OVERALL 87% Yes 7% No

"Do you feel that the NRC is justified in requiring that utilities implement a

  • drug testing program for their nuclear stations ?"

Innsbrook 92% Yes 6% No Surry 86% Yes 13% No N orthAnna 85% Yes 12% No OVERALL 87% Yes 11% No

"Do you feel that Virginia Power's Nuclear FFD Program is successful in attaining a satisfactory level of confidentiality ?"

  • Innsbrook 89% Yes 3% No Surry 83% Yes 11% No NorthAnna 74% Yes 17% No OVERALL 82% Yes 11% No f*

.* 4

Nuclear Fitness For o*u ty Program Statistics Number of Tests Industry / 1990 278,209.

Virginia Po*wer / 1990 7,923.

Virginia Power / 1991 5,179 (through 8-31-91)

Virginia Power 13,102 1-3-90 / 8-31-91

  • does not Include.4 Removals. For-Cause
  • Number of Positive Tests 2,409 32 96*

Percent Positive 0.87%

0.81%

0.62%

0.73%

Fitness For Duty 1990 Random Testing Number of Random Tests Number* of.Positive*

Random Tests

% of All Random Tests that were Positive

% of All Tests that were Positive Random Tests Industry 148,743 550 0.37%

0.20%

Virginia Power 3,871 15 0.39%

0.19%

Fitness For. Duty.

Random

  • Testing Number of Random Tests Num her of Positive Random Tests

% of All Random Tests that were Positive

% of All Tests that were Positive Random Tests Virginia Power 1990 3,871 15 0.39%

0.19%

1991 (thru *s-31-91) 2,621 10 0.38%

  • 0.19%

Fitness For Duty 1990 Pre-Access Testing Industry Virginia Power Number of Pre-Access Tests 122,491 4,008 Number of Positive 1,548 Pre-Access Tests 47

% of All Pre-Access Tests 1.26%

1.17%

that were Positive

% of All Tests that 0.56%

0.59%

were Positive Pre-Access Tests

..J..-

Fitness For Duty Pre-Access Testing Virginia Power 1990 Number of Pre-Access Tests 4,008 Number of Positive 47 -

Pre-Access Tests

% of All Pre-Access Tests 1.17%

that were Positive

% of All Tests that 0.59%

were Positive Pre-Access Tests 1991 (thru 8-31-91)

. 2,521 21 0.83%

0.41%

Fitness* For Duty 1990 For~C.ause Testing.*

Number of For-Cause Tests Number of Positive For-Cause Tests

% of All For-Cause Tests that were Positive

% of All Tests that were Positive For-Cause Tests Industry 732 214 29.2%

0.08%

Virginia Power 27 2

7.4%

0.03%

Fitness For Duty 1990 Positive Tests By. Substance Virginia Power Industry

  • Region II Marijuana 37.3%

Cocaine 31.3%

Alcohol 22.4%

Amphetamines 1.5%

Opiates 0.0%

P hencyclid ine 0.0%

Benzodiazepines 6.0%

Barbiturates 1.5%

  • Testing for BenzodiareJ!ines and Barbiturates is allowed, but not required, by the.NRC.

47.4%

47.0%

20.9%

33.0%

18.6%

16.0%

2.8%

< 1%

1.8%

3.0%

0.3%

< 1%

No. Tests No. Positive Fitness For Duty 1990 Positive Tests Industry Licensee Contractor 130,701 143,898 657 1,720 Virginia Power*

  • Licensee Con tractor 3,127 4,779 5

59 Pct. Positive 0.50%

1.20%

0.16%

1.23%

  • Includes only Random, Pre-Access, For-Cause, and Follow-Up

Fitness For Duty Positive Tests Comparison Virginia Power - 1990 Licensee Contractor Virginia Power - 1991

  • Licensee Contractor No. Tests

- 3, 12 7 4,779 2,017 3,150 No. Positive 5

59 3

29 Pct. Positive 0.16%

1.23%

0.15%

0.92%

  • Total through August 31, 1991

1990 ~ndustry Positive Test *Results By Test Type Random 42.2%

6 5 7 Positive Licensee Follow-Up 9.1%

For-Cause 10.8%

Contractors 1720 Positive Follow-Up 0.3%

For-Cause 8.3%

Contractor Positive Test Results Industry - 1990 1720 Positive Random 15.9%

Follow-Up 0.3%

For-Cause 8.3%

Virginia Power - 1990 Virginia Power - 1991

  • Pre-Access 79.7%

59 Positive For-Cause 3.4%

Random 16.9%

29 Positive Random 24.1%

For-Cause 3.4%

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