ML18152A453
| ML18152A453 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 09/08/1993 |
| From: | Buckley B Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9309160094 | |
| Download: ML18152A453 (24) | |
Text
e UNITED STATES NUCLEAR REGULATORY COMMISSION Docket Nos. 50-280, 50-281, 50-338, and 50-339 WASHINGTON, D.C. 20555--0001 September 8, 1993 LICENSEE:
Virginia Electric and Power Company (VEPCO)
FACILITIES:
Surry Power Station, Units 1 and 2, North Anna Power Station, Units 1 and 2
SUBJECT:
MEETING
SUMMARY
OF_AUGUST 25, 1993 A meeting was held with representatives of the Virginia Electric and Power Company in Rockville, Maryland on August 25, 1993.
During the meeting, the following issues were briefly discussed:
(1) integrated trending program; (2)
Technical Specifications line item improvement; (3) regulatory requirements marginal to safety; (4) Surry fire protection Technical Specifications; (5)
Surry Power Station Core Upgrading; (6) Motor Operated Valve (MOV} grouping; and (7) Nuclear Business Unit.
A summary of the discussions of each of the above issues is provided below. is a list of attendees, and meeting handouts are also enclosed.
Integrated Trending Program (Surry and North Anna)
VEPCO discussed their integrated trending program which is an internal assessment process focusing on events which, if left unattended, could lead to more significant events such as reactor trips or power reductions. Causal factors such as human error or equipment failure are evaluated to minimize or preclude recurrence.
Technical Specification Line Item Improvement VEPCO discussed various changes to the Surry and North Anna Technical Specifications that they are reviewing for submittal to the NRC.
Examples of changes under review are:
(1) Reactor Protection System and Engineered Safety Features Actuation System Surveillance Interval Increase (North Anna and Surry)
This change would increase the surveillance interval from monthly to quarterly for the analog functions.
(2) Relocate 40% of the Specifications Outside of the Technical Specifications (North Anna and Surry)
This change would implement the technical specificatfon evaluation criteria of the "Final NRC Policy Statement for Improved Technical Specifications" to relocate those specifications that are allowed to be removed from the Technical Specifications.
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Licensee {3) Single Techn;cal Specifications Book (North Anna)
Convert the Unit 1 and Unit 2 Technical Specifications books into a single book for both Units.
Make the specifications the same for both Units when justified technically.
(4)
Core Uprate (Surry)
This change would increase the allowed rated thermal power for the units by approximately 4.5%.
A discussion of other changes is provided in Enclosures 2 and 3.
Regulatory Requirements Marginal to Safety VEPCO discussed the status of various submittals which, in their judgment, are marginal to safety. The various issues discussed are delineated in Enclosure
- 4.
Fire Protection Technical Specifications (Surry)
VEPCO submitted an amendment request that would, among other things, add a fire protection license condition to each unit's operating license that varied from the NRC standard fire protection license condition in Generic Letter (GL) 86-10.
The standard NRC license condition reads as follows:
(Name of Licensee) shall implement and maintain in effect all prov1s1ons of the approved fire protection program as described in the Final Safety Analysis Report for the facility (or as described in submittals dated ---
) and as approved in the SER dated--------- (and Supplements dated
) subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Conunission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
VEPCO's submittal reads as follows:
The licensee shall implement and maintain in effect the prov1s1ons of the approved fire protection program as described in the Updated Final Safety Analysis Report and as approved in the SER dated September 19, 1979, and supplements thereto subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Conunission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
e
- Virginia Electric & 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 Riverfront Plaza, East Tower 951 E. Byrd Street Richmond, Virginia 23219 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation P.O. Box 1197 Richmond, Virginia 23209 Old Dominion Electric Cooperative 4201 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. M. L. Bowling, Manager Nuclear Licensing & Programs Virginia Electric and Power Company Innsbrook Technical Center 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 Senior Vice President Surry Power Station U.S. Nuclear Regulatory Commission Post Office Box 166, Route 1 Surry, Virginia 23883 Robert B. Strobe, 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, #2900 Atlanta, Georgia 30323 Mr. G. E. Kane, Manager North Anna Power Station P.O. Box 402 Mineral, Virginia 23117 Mr. W. L. Stewart Senior Vice President - Nuclear Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. Michael R. Kansler, Manager Surry Power Station 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
e Enclosure I Virginia Electric and Power Company August 25, 1993 Meeting List of Attendees Name Organization L. Engle NRC/NRR/PDII-2 G. Lainas NRC/NRR/DRPE
- s. Varga NRC/NRR/DRPE J. Donohew NRC/NRR/AFAR R. DePriest NRC/NRR/PDII-2 H. Berkow NRC/NRR/PDil-2 B. Buckley NRC/NRR/PDil-2 R. Prideaux VEPCO L. Girvin VEPCO M. Bowling VEPCO D. Sommers VEPCO J. Norberg NRC/NRR/EMEB T. Scarbrough NRC/NRR/EMEB C. Moon NRC/NRR/OTSB
L_icensee September 8, 1993 VEPCO's concern is that the requirement to specify the dates of the supplements would require a license amendment each time there is a change in a fire commitment rather than it being processed in a manner which would not require an amendment to the Technical Specifications.
VEPCO is deliberating on whether to withdraw the amendment or supplement it to incorporate the exact wording in GL 86-10.
Core Upgrade (Surry}
VEPCO will be performing engineering analyses to support the upgrading of the Surry core by an additional 4~% or 40 MWe.
VEPCO indicated that the associated amendment would be submitted in the July 1994 timeframe with a desired December 1994 amendment issuance date.
The NRC staff informed VEPCO that it would be difficult to meet the December 1994 completion dated.
VEPCO acknowledged the NRC schedular concerns and will take another look to determine if there are other approaches that may be taken to facilitate.the review such as meetings in advance of the submittal to discuss methodologies in conjunction with periodic discussions of how they are progression as their engineering analyses proceeds.
Motor Operated Valve Grouping (Surry and North Anna}
VEPCO commented on the recently issues Supplement No. 6 to GL 89-10 and considers that the requirements make full compliance very costly without the*
compensatory enhancement in terms of safety.
VEPCO requested a meeting in the first or second week of October 1993 to further discuss this issue.
The NRC staff was receptive to the meeting request.
Nucleir Business Unit VEPCO discussed their plans to establish a nuclear business unit to help control costs at both the Surry and North Anna nuclear facilities. The pl an, whic:h was set in motion in February 1993, will take full effect on January 1, 1994.
(Original Signed By)
. Leon B. Engle, Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation (Original Signed By)
Bart C. Buckley, Sr. Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
As stated D1stribution See next page cc w/enclosures:
- See next age OFFICE LA: PDII-2 PM: P,0.I!-2 PM: PDII-2 PD: PDII-2
/
NAME Hana tf'f-j BBucl<l ey:ms DATE 09/
/93
-09/ }5 /93 09/ t' 93 09/ <(/93 OFFICIAL RECORD COPY - DOCUMENT NAME:C:\\AUTOS\\WPDOCS\\SURRY\\NASU.MTS
I Memorandum Dated September 8, 1993 Distribution Docket File NRC & Local PDRs PDil-2 Reading T. Murley/F. Miraglia 12-G-18 J. Partlow, 12-G-18 S. Varga G. Lainas H. Berkow B. Buckley L. Engle E. Tana OGC E. Jordan J. Donohew, 11-D-23 R. DePriest J. Norberg, 7-E-23 T. Scarbrough, 7-E-23 C. Moon, ll-E.:.22 L. Plisco, EDO RII M
- S i n ku 1 e, R II e
TechAl Specifications Line Item I.rovements Under Review for Sub mitt al to the NRC Reactor Protection System Actuation System Surveillance Surry) present focus item This change would increase the quarterly for the analog functions.
and Engineered Safety Features Interval Increase (North Anna and surveillance interval from monthly to Relocate 40 I of the Specifications Outside of the Technical Specifications (North Anna and Surry)
This change would implement the technical specification evaluation criteria of the "Final NRC Policy Statement for Improved Technical Specifications" to relocate those specifications that are allowed to be removed from the Technical Specifications.
Auxiliary Feedwater Pump Surveillance Interval Increase
- 1. This change would increase the surveillance* interval from monthly to quarterly. (North Anna and Surry)
- 2. This change would also clarify the interpretation of the allowed exception to specification 4.0.4. (North Anna only)
AC Sources - Operating (North Anna and Surry)
- 1. This change would delete the requirement to test the opposite train diesel when a diesel is found to be inoperable. Testing of the opposite train would only be required if there is a possibility for common mode failure. (North Anna and Surry)
- 2. This change would delete the requirement to perform the loss of offsite power test within five minutes of completing the twenty four hour diesel run. (North Anna only)
Single Technical Specifications Book (North Anna)
Convert the Unit 1 and Unit 2 Technical Specifications books into a single book for both Units. Make the specifications the same for both Units when justified technically 1 of 3
Implement Generic Letter 91-08 (North Anna)
This change would relocate the component lists for containment isolation valves, containment penetration conductor overcurrent protective devices, motor operated valves thermal overload protection devices, and normally de-energized power circuits outside of the Technical Specifications.
Reduce the Scope of Procedure Action Requests That Require Review by the Station Nuclear Safety and Operating Committee (SNSOC) (North Anna and Surry)
This change would require SNSOC to review only new procedures and those procedure changes that require a 10 CFR 50.59 safety evaluation. This will not delete the requirement for SNSOC to review those procedures that are regulatory requirements.
Turbine Stop Valve Surveillance Interval Increase (North Anna)*
This change would increase the surveillance interval from monthly to quarterly.
Reactor Coolant System Loop Stop Valve Specs (North Anna and Surry)
This change would delete the requirement to run an isolated* reactor coolant loop on recirculation flow for ninety minutes in order to equilibrate the coolant temperature with the temperature of the cold legs prior to opening a loop stop valve.
Main Steam Trip Valve Surveillance Enhancement (Surry)
This change would m_odify the surveillance frequency from within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of criticality to in accordance with the requirements of ASME Section XI Core Uprate (Surry)
This change would increase the allowed rated thermal power for the units by approximately 4.5%.
2 of 3
e Reduce Safety Evaluation and SNSOC Meeting Minutes Reviews by the Management Safety Review Committee (MSRC) (North Anna and Surry)
This change would reduce the number of safety evaluations required to be reviewed by MSRC. The MSRC would sample safety evaluations.
ZIRLO Clad Fuel Rods (North Anna)
This change would allow the use of an additional zirconium based material, ZIRLO, in fuel assemblies for fuel rod cladding, guide thimble tubes, instrumentation tubes, and mid-span spacer grids.
Reconstituted Fuel Assemblies (North Anna)
This change would allow the use of fuel assemblies that contain solid filler rods of stainless steel, Zircaloy-4, or ZIRLO in place of standard fuel rods.
Control Room Emergency Ventilation System (North Anna)
This change would revise onsite and offsite dose consequences, and eliminate an unnecessary license condition.
Heatup/Cooldown, LTOPS, RTNDT, PTLR, Generic Letter 90-06 (North Anna)
This change would relocate the RCS pressure and temperature limits, the heatup and cooldown limits curves, and the LTOPS setpoints outside of the Technical Specifications. This material would be located in a Pressure and Temperature Limits Report (PTLR) as outlined in the new standard Technical Specifications. This change will also revise the reactor pressure vessel RTNDT limits and add the surveillance requirements for PORVs and block valves as required by NRC Generic Letter 90-06.
Low Pressure Turbine Blade Inspection Frequency (Surry)
This change would modify the surveillance interval from five calendar years to six operating years in order to coincide with the inspection of the disks and hubs.
3 of 3 Technical Specifications Line Item Improvements Under Review for Submittal to the NRC Line Item Improvement RPS and ESFAS Surveill-ance Interval Increase (North Anna and Surry)
Relocate -40% of the Specs Outside of the TS -
NRC Final Policy Statement (North Anna and. Surry)
Auxiliary Feedwater Pump Surveillance Interval Increase (North Anna and Surry)
Benefits
-estimated total savings of $116,000 per year
-eliminate unnecessary license amend-ment requests
- -make the TS more operator oriented
-increase safety focus
-estimated total savings of $11,000 per year 1.of 5 e
e
Technical Specifications Line Item Improvements Under Review for Submittal to the NRC Line Item Improvement AC Sources - Operating (North Anna and Surry)
,Single TS book (North Anna)
Implement Generic Letter 91-08 (North Anna)
Benefits
-eliminate unnecessary diesel starts e
-refueling outage schedule flex i bi 1 it y
-consistent requirements for both units
-simplify training
-reduce administrative overhead
-relocate component lists outside of TS
-simplify the use of the TS e
-eliminate potential TS amendment requests because of changes to the lists 2 of 5
Technical Specifications Line Item Improvements Under Review for Submittal to the NRC Line Item Improvement Reduce Procedure Action Request Reviews by the Station Nuclear Safety and Operating Committee (North Anna and Surry)
Turbine Stop Valve Surveillance Interval Incre~se (North Anna)
Reactor Coolant System Loop Stop Valve Specs (North Anna and Surry)
Benefits
-eliminate unnecessary administrativ#j overhead
-estimated total savings of $ TBD per year
-reduce outage critical path time 3 of 5
Technical Specifications Line Item Improvements Under Review for Submittal to the NRC Line Item Improvement Main Steam Trip Valve Surveillance Enhancement (Surry)
Core Uprate (Surry)
Reduce Safety Evaluation and SNSOC Meeting Minutes Reviews by the Management Safety Review Committee (North Anna and Surry)
ZIRLO Fuel Assembly Components (North Anna)
Benefits
-eliminate scheduling problems asso-e ciated w-ith the current surveillance requirement
-increase electrical generation
-elimina.te unnecessary administrative overhead
-improved performance characteristics 4 of 5
Technical Specifications Line Item Improvements Under Review for Submittal to the NRC Line Item Improvement Reconstituted Fuel Assemblies (North Anna)
Control Room Emergency
. Ventilation System (North Anna)
Heatup/Cooldown, LTOPS, RTNDT, PTLR, Generic Letter 90-06 (North Anna)
Low Pressure Turbine.
Blade Inspection Frequency (Surry)
Benefits
-improved fuel utilization
-improved fuel cycle costs
-eliminate an unnecessary license condition
-relocate* TS limits arid setpoints to a licensee controlled document
-Generic Letter compliance
-enhance the inspection schedule to coincide with other related inspections 5 of 5
VIRGINIA POWER H
Submitted Regulatory Reduction Items I AUGUST 23, 1993 J
Submitted Commitment Changes
- 11\\j j
.' ~* 1 *!
I AUGUST 23, 1993 J VIRGINIA POWER
,.ITEM SPS CONTROL ROOM DESIGN REVIEW REASSESSMENT REG GUIDE 1.97 / P250 DATA ISOLATION
.. AFW PUMP INSPECTION DELETION SPS STEAM GENERATOR STORAGE f ACILITY FIL TEA SPS IRS PUMP INSPECTION DELETION SPS EDSFI ELIMINATION GL 89-10 BUTTERFLY VALVES
- NAPS BREAKER BOLT INSPECTION FREQUENCY
- STATUS !ESTIMATED SAVINGS APPROVED
$11,409,400 APPROVED
$2,000,000 APPROVED*
$190,000 / YR APPROVED
$1000 / YR APPROVED
$170,000 I YR APPROVED
$323,000 DENIED
$475,000 IMPLEMENTED $10,000 / YR 3/5/93
I AUGUST 23, 1993
- 1 VIRGINIA POWER Submitted Commitment Changes Continued ITEM STATUS ESTIMATED SAVINGS PC BASED PIPE STRESS ANALYSIS APPROVED
$48,000 / YR NAPS REG GUIDE 1.97 SUBMllTED
$89,000 STEAM GENERATOR PRESSURE 3/31/93*
RECORDER EXCEPTIONS GL 89-10 MOV TESTING SUBMITIED TBD SCHEDULE
~29~3 RELIEF REQUEST FOR SPS SUBMITIED
$670,000 PRESSURIZER CIRCUMFERENTIAL 8/11/93 WELD INSPECTION
I AUGUST 23, 19931 VIRGINIA POWER Submitted Technical Specification Changes ITEM SPS RCS LOOP STOP VALVE INTERLOCK NAPS STEAM GENERATOR INSPECTION SCOPE SPS SENSITIZED STAINLESS STEEL PIPING INSPECTIONS NAPS TYPE A SCHEDULE RELIEF PROCEDURE REVIEW FREQ SEMI-ANNUAL EFFLUENT
.. RELEASE REPORT FREQUENCY TO.ANNUAL QA AUDIT FREQUENCY SUBMITTED APPROVED SUBMITTED 7/2/93 SUBMITTED 7/2/93 SUBMIITED 7/2/93 SUBMIITED 7/8/93 SUBMITIED.
7/16~93 SUBMITIED 7/20/93 e
ESTIMATED SAVINGS TBD
$100,000
- $129,000 / YR
$750,000
$142,000 I YR
$7,000 I YR
$450,000 I YR
I AUGUST 23, 1993, I VIRGINIA POWER Submitted Exemption Requests ITEM SUBMITTED ESTIMATED SAVINGS
$200,000 I YR.
EXERCISE EXEMPTION 1993 NAPS EP ANNUAL APPROVED
$200,000 I YR EXERCISE EXEMPTION APPENDIX J - CONTAINMENT SUBMITTED PREVENT INTEGRATED LEAK RATE 3/1/93 UNNECESSARY TESTING TESTING
VIRGINIA POWER I AUGUST 23, 1993. I Submitted Generic Rulemaking ITEM ST A TUS.
EMERGENCY PREPAREDNESS SUBMITIED ANNUAL EXERCISE 12/9/92 ESTIMATED SAVINGS
$200,000 I YR.
VIRGINIA POWER II ITEM I AUGUST 23, 1993
- 1 Items Referred to NUMARC
- t, DEFINIT~ON OF SAFETY RELATED -
STATUS SUBMITTED 8/17/93 J
VIRGINIA POWER I AUGUST 23, 1993 ]
Present Focus Items
Present Focus Items I AUGUST 23, 1993
- 1
.
$240,000/YR 8/93 -
10 CFR 50.54 RULEMAKING RULEMAKING
$60,000 9/93 (DECREASE AUDIT FREQUENCY AND ELIMINATE NRC APPROVAL OF PLAN CHANGES FOR EP, FFD
~ND SEC}
SQUG UTILIZATION FOR COMMITMENT
$80,000 10/93 QUALIFYING RG 1.97 EQUIPMENT CHANGE POST ACCIDENT SAMPLING COMMITMENT
$80,000 ONE 10/93 SCQPE REDUCTION CHANGE TIME PLUS
$120,000/YR REVIEW OF FIRE WATCH COMMITMENT
$380,000/YR 10/93 REQUIREMENTS CHANGE APPENDIX R / APPENDIX A FIRE LICENSE TBD 12/93 PROTECTION COMMITMENTS AMENDMENT REVIEW
II Present Focus Items (Continued) I AuGusr23, 1993 I '
VIRGINIA POWER llEM ACTION EST SAVINGS SCHED REDUCE SNSOC REVIEW OF TS CHANGE
$190,000/YR 10/93 PROCEDURES AND MSRC REVIEW OF SAFETY EVALS AND SNSOC MINUTES DECREASE AFW PUMP TS CHANGE
$11,100/YR 10/93 TESTING FREQUENCY DECREASE FIRE PUMP TEST COMMITMENT TBD 11/93 FREQUENCY CHANGE DECREASE GER FREQUENCY TBD TBD 12/93 DECREASE RPS I ESF TS CHANGE
$116,200/YR 1/94 FUNCTIONAL TESTING FREQUENCY REDUCE EP STAFF COMMITMENT
$750,000/YR 1/94 AUGMENTATION CHANGE GRADED QA IMPLEMENTATION COMMITMENT TBD 3/94 ELIMINAT~ON OF CHANGE OVERCOMMITMENTS TO 10 CFR 50
- APP 8