ML20117C637
| ML20117C637 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Hatch |
| Issue date: | 06/30/1983 |
| From: | Rivenbark G Office of Nuclear Reactor Regulation |
| To: | Carter J, Harold Denton, Eisenhut D NRC |
| Shared Package | |
| ML20114F930 | List:
|
| References | |
| FOIA-84-616 TAC-51908, NUDOCS 8505090478 | |
| Download: ML20117C637 (1) | |
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June 30,1983 Docket No. 50- 366 MEMORANDUM FOR:
H. Denton T. Speis J. Carter R. Vollmer E. Case D. Eisenhut R. Mattson S. Varga R. Purple H, Thompson D. Vassallo T. Novak J. Sniezek R. Clark G. Lainas T. Ippolito D. Crutchfield F.. Mi ra g.l ia. _.
C. Heltemes THRU:
John F. Stolz, Chief, Operating Reactors Branch #4, Division of Licensing FROM:
George Rivenbark, Promect fianager Operating Reactors Branch #4, Division of Licensing
SUBJECT:
DAILY HIGHLIGHT Hatch Nuclear Plant, Unit 2 On June 22, 1983, Georgia Power Company. informed Region II that 8 high energy pipe restraints identified in the Hatch Unit 2 FSAR.as being installed, are in fact, not installed. The restraints are missing from the reactor core isolation cooling, reactor water cleanup, control rod drive, and auxiliary steam systems.
They were discovered to be missing during another unrelated design activity.
The reactor is currently shutdown for maintenance refueling but is scheduled to startup this weekend (July 2-3). The licensee proposes to startup and operate-without the restraints until the next refueling outage. At Region II's request and by letter dated June 28, 1983, the licensee submitted a discussion of the event and a justification for operation of the plant without the pipe restraints until it can design and install them.
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Region II, on June 29, 1983, requested that NRR evaluate the licensees proposal to operate the plant without the restraints.
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November 7,1983 Facility Name: Three Mile Island, Unit No. 1 Licensee: GPU Nuclear Corporation NRR Project Manager: James A. Van Vliet I.
Introduction This report presents the results of an evaluation of the licensee, GPU Nuclear Corporation in the functional area of licensing activities.
It is.
intended to provide NRR's input to the SALP review process as described in NRC Manual Chapter 0516. The review covers the period 10/1/82 to 9/30/83.
The basic approach used for this evaluation was to first select a number of licensing issues which involved a significant amount of staff manpower.
Comments were then solicited from the staff. In most cases the staff applied the evaluation criteria for the performance attributes based on their experience with the licensee or his products. Finally, this infor-mation was assembled in a matrix which allowed an overall evaluation of the licensee's performance. This evaluation is based on staff input from branches in four NRR divisions.
II.
Suninary of Results NRC Manual Chapter 0516 specifies that each functional area evaluated will be assigned a performance category based on a composite of a number of attributes. The single final rating to be tempered with judgement as to the significance of the individual elements.
Based on this approach, the performance of GPU Nuclear Corporation in the functional area - Licensing Activities - is rated category 2.
III. Criteria Evaluation criteria, as given in NRC Manual Chapter Appendix 0516 Table 1, were used for this evaluation.
IV.
Performance Analysis i
The licensee's performance evaluation is based on a consideration of seven
- attributes as given in the NRC Manual Chapter. For most of the licensing actions considered in this evaluation, only three or four of the attributes were of significance. Therefore, the composite rating is heavily based on the following attributes:
- Management involvement
- Approach to resolution of technical issues
- Responsiveness Of the remaining attributes of:
- Enforcement History
- Reportable Events t
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- Staffing
- Training only staffing was judged to apply to the licensing activities evaluated.
The evaluation was based en our evaluation of the following licensing activities:
- Response to NUREG-0737 Items
- Fire Protection Program (Appendix RRequirements)
- Steam Generator Recovery Program
- Pre-Restart License Amendments
- Seismic Qualification of Auxiliary Feedwater
- Licensed Operator Requalification Program Changes
- Inadequate Core Cooling Instrumentation A.
Management Involvement in Assuring Ouality
/
Overall rating for this attribute is category 2.
All activities were rated as category 2, except for the steam generator recovery program which was rated category 1.
In general, the level of management involvement has been appropriate for the significance of the issue.
Prior planning, prioritization of activities and corporate management involvement in site activities are evident.
In the case of the steam generator recovery program, an issue of high company priority, safety significance, and public visibility, involvement by the highest levels of GPU management has been readily apparent.
B.
Approach to Resolution of Technical Issues from a Safety Standpoint Overall rating for this attribute is category 2.
Fire protection and the steam generator recovery program were rated category 1, and the remaining activities were rated category 2.
The licensee's understanding of the issues has been generally apparent and the proposed resolutions have been generally conservative and sound.
In particular the licensee's approach to resolution of fire protection (Appendix R requirements) demonstrates a clear understanding of the
. technical issues; leading to technically sound, thorough approaches for resolution of the issues. The licensee's steam generator recovery program has continued to be thorough, well planned, conservative and technically sound. For both of these issues, the licensee has frequently posed questions and requested clarifications from the staff on technical or licensing aspects of the issues. This has tended to assure continued clarity of the issues to be resolved and miminized false starts, rework, etc.
C.
Responsiveness to NRC Initiatives Overall rating for this attribute is category 2, with all activities rated category 2.
A noted trend is that the licensee is most responsive to those
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'c issues that licensee considers having higher priority (those issues impacting restart). Issues to which licensee assigns lesser priorities periodically require submittal schedule extensions. Although it is not an activity listed in the evaluation matrix, the Control of Heavy Loads is oneissue for which significant submittal extensions have been necessary.
Licensee responses to NRC initiatives are generally sound and thorough; and acceptable resolutions are generally proposed.
D.
Enforcement History Not applicable.
E.
Reporting and Analysis of Reportable Events Not applicable.
F.
Staffing (Including Management)
Staffing was only evaluated for one activity, thus there is insufficient basis for a meaningful overall rating of this attribute. Staffing was rated category 1 for the steam generator recovery program. Consistent with the scope and priority of the steam generator recovery) program, th licenseehasdedicatedamplestaffing(includingmanagement of appropriate qualifications.
G.
Training Training was not evaluated for any of the activities evaluated. Thus there is no basis for evaluation.
4 V.
Conclusions Based on an NRR evaluation of eight licensing activities during the period October 1,1982 through September 30, 1983, the overall performance rating for GPU Nuclear licensing activities for Three Mile Island Nuclear Station, i
Unit 1 is category 2.
The overall rating for each evaluated attribute is category 2.
The individual attribute ratings for each activity all fall into categories 1 and 2.
No major deficiencies affecting licensing activities became apparent during the evaluation period. The licensee generally devotes an adequate level of management involvement to licensing activities; the licensee's approach to the resolution of technical issues is generally sound and conservative; and, the licensee is generally responsive to NRC initiatives.
J s A. Van Vliet, Project Manager Operating Reactors Branch #4 Division of Licensing
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y lHI-l EVALUATION !! ATRIX Review Licensing Management Approach to Responsiveness Enforcement Reporta6le Staffing Iraining 4
l Branch Action involvement Resolution of to NRC History Events luvulved lecimical Issues Initiatives l
liHAll Response to l
NUREG-0737 Items 2
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N/A N/A No basis N/A 1
3Sh Fire Protection CEB Program (Appendix 2
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N/A N/A No basis N/A Rrequirements)
TEB steam Generator URAll Recovery Program i
I 2
N/A N/A I
N/A T/A '
Pre-Restart License Amendments 2
2 2
N/A N/A No basis N/A
~ h8 Seismic Qualification 0R of Auxiliary Feed-2 2
2 N/A N/A No basis N/A water Tyu Licensed operator Requalification 2
2 2
N/A N/A No basis N/A Program Changes EPh Inadequate Core Cooling Instru-2 1
2 N/A N/A No basis N/A mentation DVERALL 2
2 2
N/A N/A No basis N/A O
September 6, 1983 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-II-83-72
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This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or
. public interest significance.
The information is as initially received without verifi-l cation or evaluation, and is basically all that is known by the Region II staff on this date.
FACILITY:
Mississippi Power & Light Company Licensee Emergency Classification:
Grand Gulf Unit 1 X Notification of Unusual Event Docket No.50-416 Alert Port Gibson, Mississippi Site Area Emergency General Emergency Not Applicable
SUBJECT:
DIESEL GENERATOR ENGINE FIRE A diesel generator engine fire, caused by a ruptured fuel oil supply line which sprayed oil on the hot exhaust manifold, occurred at 2:36 p.m. (CDT) on September 4 on the Division 1 diesel generator engine. The diesel was running at 25 percent load for testing.
Two other generators were not affected by the fire.
P;rsonnel in the diesel room observed the event.
The water deluge system failed to function automatically but was manually activated to extinguish the fire.
Offsite assistance was not requested.
The licensee is investigating the cause of the system failure.
The licensee declared an Unusual Event at 2:47 p.m. (CDT) and terminated the declaration at 3:56 p.m. (CDT).
The licensee is investigating the extent of damage to the diesel and assessing the delay this may cause to plant restart. The reactor is in cold shutdown awaiting restart for power ascension testing.
Media interest has occurred. The licensee does not plan to issue a news release but is responding to local media inquiries.
The NRC does not plan to issue a news release.
The State of Mississippi has been informed.
Th2 NRC received initial notification of this occurrence by telephone to the headquarters duty officer at 4:22 p.m. (EDT) on September 4.
This infortnation is current as of 8:00 a.m. on September 6.
Contact:
C. A. Julian, RII 242-5535 D. M. Verrelli, RII 242-5526 6f(
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