IR 05000275/1987012
| ML16341E159 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/26/1987 |
| From: | Johnston K, Mendonca M, Narbut P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16341E158 | List: |
| References | |
| 50-275-87-12-MM, 50-323-87-11, NUDOCS 8704210091 | |
| Download: ML16341E159 (8) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report Nos. 50-275/87-12 and 50-323/87-11 Docket Nos.
50-275 and 50'-323 License No.
DPR 80 and
Licensee:
Pacific Gas and Electric Company 77 Beale Street, Room 1451 San Francisco, California 94106 Facility Name:
Diablo Canyon Nuclear Power Plant Units 1 and
Inspection at:
Diablo Canyon Site, San Luis Obispo County, California Inspection Condu ed:
M rch 6, 1987 Inspectors:
E. J hnst n, Resident Inspector P.
N rbu Senior Resident Inspector I/
Approved by:
>
-
,
u M. M. Mendonca, Section Chief Date Signed 7zs IF Date Signed Date Signed
~Summa r Mana ement meetin on March 6 1987 (Re ort Nos. 50-275/87-12 and 50-323/87-11 A management meeting was held on March 6, 1987 to discuss recent plant events and apparent problem areas that have developed since the last management meeting held on November 24, 1986.
870421009i 870330 PDR ADOCK 05000275 Q
MANAGEMENT MEETING DETAILS Attendees Pacific Gas and Electric Company:
'.
A. Maneatis, President J.
D. Shiffer, Vice President, Nuclear Power Generation R.
C. Thornberry, Plant Manager, Diablo Canyon Power Plant J.
C. Carroll, Manager, Nuclear Operations Support B. S.
Lew, Director Nuclear Regulatory Affairs G.
H. Moore, Manager, Nuclear Engineering and Construction Services S.
M. Skidmore, Manager, (}uality Assurance W. Raymond, Assistant Vice President, Nuclear Power Generation J.
M. Gisclon, Assistant Plant Manager, Technical Services J. A. Sexton, Assistant Plant Manager, Plant Superintendent J.
D. Townsend, Assistant Plant Manager, Support Services C. L. Eldridge, guality Control Manager ( In Training)
R.
P.
Powers, Acting guality Control Manager C. Coffer, Operational Licensing Manager D. S. Aaron, Director Auditing D. A. Taggart, Director guality Support L. F.
Womack, Operations Manager D. B. Miklush, Maintenance Manager M. J. Angus, Work Planning Manager W. J. Keyworth, Emergency Planning Supervisor T. K. Greble, Regulatory Compliance Supervisor D. A. Vosburg, Operations Shift Supervisor R. S. Weinberg, News Service Representative United States Nuclear Regulatory Commission:
J.
B. Martin, Regional Administrator D. F. Kirsch, Director, Division of Reactor Safety and Projects S, A. Varga, Project Director, Directorate No. 3, NRR M. M. Yiendonca, Section Chief, Project Section I H.
E. Schierling, Project Manager, NRR P.
P. Narbut, Senior Resident Inspector, Diablo Canyon L. M. Padovan, Resident Inspector, Diablo Canyon K. E. Johnston, Resident Inspector, Diablo Canyon Yieetin Summar The meeting convened at approximately 9:00 a.m.
on March 6, 1987 at the Diablo Canyon site.
Mr. J.
B. Martin opened the meeting by indicating that the purpose of the meeting was to have an open discussion, in a setting other than a
SALP meeting or an enforcement conference, of recent plant events and licensee performance.
Mr. Maneatis responded that he was encouraged by having regular meetings which give the licensee an opportunity to explain recent performance and take comments from the NRC.
Mr. Maneatis introduced Mr. Vosburg to discuss recent reactor trip t oCs
Hr. Vosburg discussed four reactor trips that had occurred since the November 24, 1986 Management Meeting.
The first trip discussed was the Unit 1 trip from 7% power of December 28, 1986.
The trip was, in part, due to slight low power flow instabilities causing the spurious flickering of steam flow-feed flow bistables.
Mr. Moore answered questions from the NRC concerning what actions the licensee is taking to prevent spurious flickering of the steam flow-feed flow bistable.
The licensee is currently investigating the possibilities of'eplacing the flow transmitters with more accurate designs, raising the low power flow mismatch setpoint, or eliminating the mismatch input to the reactor trip system.
The second trip discussed occurred one half hour after the first trip while the plant was in Mode 3.
Several things were conducted in an effort to reduce cooldown.
First, the reactor trip breakers were closed to allow the turbine generator to be latched; then the auxiliary feedwater was reduced to the point where a low-low steam generator level trip occurred.
Mr. Martin asked if lessons learned as a result of the second trip has been passed on to the operators and was informed that all reactor trips are covered in requalification training.
The third trip discussed by Mr. Vosburg was the January 5, 1987 Unit I trip from 30K power due to a loss of turbine governor valve electro-hydraulic (EH) system pres.ure.
It was noted that the licensee is evaluating the possibility of a design change that would initiate reactor trip on turbine trip at greater than 504 power rather than the current 10% power.
The fourth trip discussed occurred on February ll, 1987 to Unit 1 when it tripped from 30K power on high steam generator level as a result of a feedwater regulator valve control problem.
The licensee di cussed their plans to update their control systems.
Mr.
Martin suggested that the licensee investigate the performance improvements that Portland General Electric had achieved subsequent to a difficult startup in 1984.
The utility had found ways to avoid situations where the steam generator level control system becomes unstable and has not had a feedwater control related reactor trip since that time.
Mr. Vosburg concluded with a. briefing on the Unit 2 reactor trip of the night prior to the meeting.
The trip occurred when the licensee attempted to bring the main turbine up to rated speed using auxiliary feedwater
.
The auxiliary feedwater system was used at the limit of its flow capacity and the unit tripped on low low steam generator level.
Mr. Sexton briefly discussed the January 2 and 10, 1987 main turbine oil fires and the root cause investigation that followed.
Mr. Keyworth discussed the notification complications and what procedural modifications have been implemented to prevent recurrence.
Mr. Womack began his presentation with a discussion of inadvertent technical specification violations resulting from operators being unaware of technical specifications applicable to component being taken out of service.
Mr. Womack related that an investigation is in progress to determine the feasibility of a computerized technical specification-system/component tracking system.
Mr. Womack then discussed the
<<la
licensee's event investioation and problem resolution program.
The licensee is in the process of formalizing their event recovery procedure so that all involved individuals will be required to write down actions and observation
, including a debrief after all events.
Current discussion now centers on determining the level the event recovery procedure should be initiated.
Mr. Nartin noted that one Region V licensee has incorporated a three level program and suggested that PGLE discuss event recovery with them.
Mr. Martin also noted that this utility has initiated an accountability program which has greatly reduced personal errors.
Mr.
Shiffer pointed out that Assistant Plant Managers are now required to be accountable for the resolutions included in nonconformance reports.
Mr.
Martin questioned whether the licensee was learning from experience and that they appeared to be behind on root cause identification programs.
Mr. Martin encouraged the licensee to be aggressively self-critical in these areas.
Nr. Angus discussed the backlog of action requests (AR's).
The licensee began an evaluation in November cf 1986 to determine the ease of use of ARs, to analyze the backlog of ARs and to identify the total effectiveness of the program.
This evaluation is'cheduled for.
completion later this year.
Nr. Powers discussed the licensee's maintenance of seismic qualification in response to the resident inspectors'ecent i.-,.spection findings (Inspection Report Hos. 50-275/87-10 and 50-323/87-09).
The licensee has initiated a program aimed at increasing their sensitivity to seismic qualification issues by including seismic interaction topics in general maintenance training.
In addition, the licensee is establishing what pressurized gas bottles need to be stored permanently at locations around the site for the convenience of testing.
Yr. Townsend discussed the Unit I refueling outage
"lessons learned" program.
The program identified 200 items to be resolved for the Unit 2 refueling outage scheduled to commence the beginning of April.
Nr.
Townsend also discussed the licensee's efforts to improve upon its last restart from refueling.
In this effort, Mr. Gisclon visited Trojan this past January to discuss their successful restart program.
Mr. Varga discussed the forthcoming NRC reorganization and NRR's change in focus from being a licensing organization to a operations support organization.
Nr. Varga then noted two significant licensing issues that NRR had been working on, the spent fuel rack hearings and the long term seismic program.
Mr. Martin suggested that the licensee and NRC should have continuing discussions to ensure the specific goals for the long term seismic program were monitored and appropriate.
Mr. Varga and Nr.
Naneatis concurred with this proposal.
Yr. Martin concluded by stating that the licensee was in the formative years of operation and encouraged the licensee continue critical evaluations of their performance.
The meeting so concluded at about I:00 p.m.
on March 6, 1987.