ML18142A214
| ML18142A214 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/18/1985 |
| From: | Neighbors J Office of Nuclear Reactor Regulation |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8503250359 | |
| Download: ML18142A214 (8) | |
Text
"*
e Docket Nos. 50-280 and 50-281 MEMORANDUM FOR:
THRU:
FROM:
SUBJECT:
iMa rch 18, 1985 DISTRIBUTION Docket File NRC PDR L PD~ - --
ORB#l Rdg Memo File GLainas SVarga CParrish JDNeighbors Division of Project and Resident Programs, Region II Gus C. Lainas, Assistant Director for Operating Reactors Division of Licensing Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing Joseph D. Neighbors, Project Manager Operating Reactors Branch #1 Division of Licensing PERFORMANCE EVALUATION FOR SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE (SALP) FOR VIRGINIA ELECTRIC AND POWER COMPANY'S (VEPCO) SURRY POWER STATION, UNIT NOS. 1 AND 2 - SEPTEMBER 1, 1983 TO FEBRUARY 28, 1985 Enclosed is the NRR input for the SALP report for VEPCO in the functional area of licensing activities related to Surry Power Station, Units 1 and 2.
Staff personnel who have been substantial contact and involvement with VEPCO provided the basis for the input.
In addition to licensing actions handled by NRR, licensing issues handled by the Region were also included.
A draft was circulated to all the NRR Divisions for comments.
All comments received were considered in the final version.
As discussed in the enclosure, our evaluation was conducted according to NRR office letter No. 44 dated January 3, 1984, and NRC Manual Chapter 0516, Systematic Assessment of Licensee Performance.
Enclosure:
Input for SALP Report cc w/enclosure:
H. Thompson CONTACT:
J. D. Neighbors X24837 ORB~:
JON ors;ps 3/t /
8503250359 850318 --
PDR ADOCK 05000280 G
PDR Sincerely,
/s/JDNeighbors Joseph D. Neighbors, Project Manager Operating Reactors Branch #1 Division of Licensing AD (J,,*DL GL~s 31tt85
Docket Nos. 50-280 and 50-281 e
e UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FACILITY:
Surry Power Station, Unit Nos. 1 and 2 LICENSEE:
Virginia Electric and Power Company EVALUATION PERIOD:
September 1, 1983 to February 28, 1985 PROJECT MANAGER:
Don Neighbors I. INTRODUCTION This report contains NRR's input to the SALP review for the Surry Power Station Units Nos. 1 and 2.
The assessment of the licensee's performance was conducted according to NRR Office Letter No. 44, NRR Inputs to SALP Process, dated January 3, 1984.
This Office Letter incorporates NRC Manual Chapter 0516, Systematic Assessment of Licensee Performance.
II.
SUMMARY
NRC Manual Chapter 0516 specifies that each functional area evaluated will be assigned a performance category {Category 1, 2 or 3) based on a composite of a number of attributes.
The single final rating to be tempered with judgment as to the significance of the individual elements.
Based on this approach, the performance of Virginia Electric and Power Company in the functional area - Licensing Activities - is rated Category 1.
II I. CRITERIA The evaluation criteria used in this assessment are given in NRC Manual Chapter 0516 Appendix, Table 1, Evaluation Criteria with Attributes for Assessment of Licensee Performance.
IV. METHODOLOGY This evaluation represents the integrated inputs of the Operating Reactor Project Manager (0RPM) and those technical reviewers who expended significant amounts of effort on the Surry Power Station, Units 1 and 2 licensing actions during the current rating period.
Using the guidelines of NRC Manual Chapter 0516, the 0RPM and each reviewer applied specific evaluation criteria to the relevant licensee performance attributes, as delineated in Chapter 0516, and assigned an overall rating category (1, 2 or
- 3) to each attribute.
The reviewers included this information as part of each Safety Evaluation Report input transmitted to the Division of Licensing.
The 0RPM, after reviewing the SALP inputs of the technical reviewers, combined this information with his own assessment of licensee performance and, using appropriate weighting factors, arrived at a composite rating for the licensee. This rating also reflected the comments, if any,
of the NRR Senior Executive assigned to the Surry Power Station, Units 1 and 2 SALP assessment. A written evaluation was then prepared by the 0RPM and circulated to NRR management for comments which, if provided, w~re incorporated in the final draft.
The basis for this appraisal was the licensee 1s performance in support of licensing actions that were either completed or had a significant level of activity during the rating period. There were a total of 94 active actions at the beginning of the rating period for the Surry Plants. Actions were added to the multi-plant and plant specific actions for a total of 170 actions by the end of the rating period.
We have closed 89 actions during the rating period and have 81 active actions at the end of this rating period.
These actions and a partial list of completions consisting of
.amendment requests, exemption requests, responses to generic letters, TM!
items, and licensee initiated actions are:
72 Multi-Plant Actions (28 completed).
Some of the completed actions in this category are:
0 Adequacy of Station Electric Distribution System Voltages (B-48) 0 Natural Circulation Cooldown (B-66) 0 ESF Filters (C-04) 0 Asymmetric LOCA Loads (D-10) 0 HELB and Consequential System Failure (D-15) 0 NUREG-0737 Technical Specifications (Generic Letter 82-16) (B-72)
~ Control of Heavy Loads (Phase I) (C-10) 0 Appendix J (RETS) Technical Specifications (A-02)
~ Fuel Handling Accident Inside Containment (C-07) 0 NUREG-0737 Technical Specifications (Generic Letter 83-37) (B-83) 0 Detailed Control Room Design Review Program Plan.
(F-08) 58 Plant Specific Actions (41 completed).
Some of the completed actions in this category are:
0 Exemption on Fire Protection Schedule 0
F~ Hand Rod Insertion Limits Technical Specifications
~ Containment Isolation Valves Technical Specifications 0
!SI Second Ten Year Interval (Surry 1) 0 Reduction of Boron Concentration in BIT 0
Extend Burnup to 45,000 MWD/MTU 0
ASME Relief Requests
~ Core Reload Methodology Audit 0
Appendix R Exemptions 0
Snubbers 40 TMI (NUREG-0737) Actions (20 completed).
Some of the completed actions in this category are:
0 Plant Shielding (II.B.2.2) 0 Post Accident Sampling (II.B.3.2) 0 Inadequate Core Cooling Guidelines (I.C.1.2.A) 0 Thermal Mechanical Report (II.K.2.13) 0 Potential for Voiding in RCS (II.K.2.17)
V. ASSESSMENT OF PERFORMANCE ATTRIBUTES The licensee's performance evaluation is based on a consideration of four of the seven attributes specified in NRC Manual Chapter 0516.
These are:
-- Management Involvement and Control in Assuring Quality
-- Approach to Resolution of Technical Issues from a Safety Standpoint Responsiveness to NRC Initiatives Staffing For the remaining three attributes (enforcement, reportable events, and training and qualification effectiveness), no basis exists for an NRR evaluation for the functional area of Licensing Activities.
A. Management Involvement and Control in Assuring Quality The licensee continues, as during the last period, to demonstrate active partici~ation in licensing activities and has kept abreast of current and anticipated (with one exception) licensing actions.
In particular, the licensee's management at times has proposed actions to facilitate licensee understanding and NRC review of issues such as Appendix R exemptions (where technical staff routinely met during development of the exemption requests).
The licensee' management consistently exercised good control over its activities and has maintained effective communication with the project
manager even though experiencing several changes in management staff during this period.
As implied above, one area where management attention could be increased is the area of potential amendment requests so that situations could be avoided that require rapid response.
For instance, amendment number 101 (Snubber Inspection Interval) on Surry 2, could have been submitted sooner and allowed more t.ime for public notice.
A rating of 1 is assigned to this attribute.
B.
Approach to Resolution of Technical Issues from a Safety Standpoint The interaction of the licensee, including visits and management discussions/meetings, with the NRC staff, have resulted in clear understanding of safety issues.
Sound technical approaches are taken by the licensee's technical staff toward their resolution. Conservatism is being exhibited in relation to significant safety issues on a routine basis.
Thoroughness in the approach to the technical issues has been demonstrated by the number and complexity of the licensing actions completed during this
- .e.*
- peri ad.
Consistently sound technical justification is provided by the licensee for deviations from staff guidance.
The good communications between the licensee and NRC staff have been beneficial to both in the processing of licensing actions and minimizing the need for additional information.
On the basis of these observations, a rating of 1 is assigned to this attribute.
C.
Responsiveness to NRC Initiatives The licensee has been responsive to NRC initiatives in all but one or two situations. One in particular relates to a response on a Technical Specification related to high energy lines. However, in all other instances the licensee has made every effort to meet the established commitments as illustrated by its responses to TMI action items, Appendix Rand Environmental Qualification of safety related electrical equipments.
When original commitments could not be met, the licensee is prompt to discuss the problems and provide new schedules.
Based on the above considerations, the overall rating of 1 is assigned to this attribute.
D. Enforcement
- No basis exists for an NRR evaluation of this attribute.
E. Reportable Events No basis exists for an NRR evaluation of this attribute.
e F. Staffing The licensee has a licensing staff which is sensitive to the requests by the NRC and seeks to assure timely responses.
The licensee, during this period, made a realignment in its management organization to provide more emphasis on licensing.
A rating of 1 is assigned to this attribute.
G. Training and Qualification Effectiveness No basis exists for an NRR evaluation of this attribute.
VI. CON CL US ION A complete performance rating of 1 has been assigned by NRR for the SALP evaluation for the current rating period.
INFORMATION TO BE ADDED TO SECTION V OF THE SALP REPORT "SUPPORTING DATA AND
SUMMARY
- 1.
NRR/Licensee Meetings Boron Reduction Review Environmental Qualification IST Fuel Reconstitution Appendix R Status Director (DL) Briefing
- 2.
NRR Site Visits/Meetings Regulatory Effective Review Inadequate Core Cooling Audit Heavy Loads DCRDR
- 3.
Corrmission Briefings None
- 4.
Schedular Extensions Granted EQ Completion Extension
- 5.
Reliefs Granted ASME !SI 2nd 10 year ASME ISI,Section XI relief ASME ISI, Section, XI relief ASME ISI, Section, XI relief ASME !SI, Section, XI relief
- 6.
Exemptions Granted Appendix R, Schedule
- 7.
Licensing Amendments Issued Amendment Numbers 90/89 91/90 92/91 Title Fractional Power Limit Containment Isolation Valves ESF Filters 09/21/83 03/19/84 09/24/84 10/11/84 10/28/85 02/05/85 9/19-23/83 05/03/84 07/26/84 11/09/84 12/14/84 01/24/84 02/28/84 05t07/84 05/17 /84 11/30/84 19/09/83 Date 09/22/83 11/14/83 01/17/84
94/93 95/94 96/95 97/96 98/97 99/98 100/99 101/100
--/101 e Snubbers Boron Injection Tank Cone.
Fire Pump Head Appendix I (RETS)
Aux. Feedwater Pump Charging Pump NUREG-0737 (GL 83-37)
Rod Drop Times Snubber Inspection Interval
- 8.
Emergency Technical Specifications Issued Amendment Numbers Title e
--/101 Snubber Inspection Interval -
- 9.
Orders Issued Confirmatory Order - Implementation of Supplement 1 to NUREG 0737
- 10.
NRR/Licensee Management Conferences Director (DL) Briefing 01/31/84 02/24/84 04/20/84 06/19/84 10/12/84 10/12/84 10/15/84 01/22/85 02/01/85 Date 02/01/85 05/12/84 02/05/85