IR 05000424/1987056
| ML20237D480 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/16/1987 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | James O'Reilly GEORGIA POWER CO. |
| References | |
| NUDOCS 8712230292 | |
| Download: ML20237D480 (30) | |
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DEC 161987 Docket No. 50-424 License No. NPF-68 Georgia Power Company ATTN: Mr. James P. O'Reilly Senior Vice President-Nuclear Operations P. O. Box 4545 Atlanta, GA 30302 Gentlemen:
SUBJECT:
RESOLUTION OF ENFORCEMENT ISSUES (INSPECTION REPORT 50-424/87-56)
This letter refers to the Enforcement Conference conducted, at our request, at NRC Region II office on October 21, 1987.
This meeting concerned two potential violations described in NRC Inspection Report No. 50-424/87-56.
These violations represented Technical Specification compliance regarding residual heat removal system and proper reporting.
Our concerns were expressed to you at the meeting and your positive response I
to our concerns was appreciated.
The enclosure documents the final deliberation of both potential violations.
These violations are being closed based on extensive staff review of the information provided at the conference and as documented in post conference
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correspondence.
It is our opinion that this meeting and the information exchanges have provided a better mutual understanding of the inspection findings and enforcement issues.
The enclosures also document the identifica-tion of a violation regarding a failure to take prompt corrective actica in response to an NRC Information Notice.
Since in the staffs opinion the violation meets the five criteria as specified in the enforcement policy no Notice of Violation is being issued.
Should you have any questions concerning this letter, please contact this office.
Sincerely
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Original Signed by Luis A. Reyes /for i
J. Nelson Grace Regional Administrator Enclosures:
(See page 2)
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8712230292 871216 PDR ADOCK 05000424
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Georgia Power Company
DEC 101987 Enclosures:
1.
Enforcement Conference Summary 2.
GPC Presentation 3.
List of Attendees cc w/encls:
P. D. Rice, Vice President, Project Director C. W. Hayes, Vogtle Quality Assurance Manager G. Bockhold, Jr., General Manager, Nuclear Operations L. Gucwa, Manager, Nuclear Safety and Licensing J. A. Bailey, Project Licensing Manager D. Kirkland, III, Counsel, Office of the Consumer's Utility Council D. Feig, Georgians Against Nuclear Energy bec w/encls:
E. Reis, OGC M. Miller, NRR M. Sinkule, RII DRS Technical Assistant NRC Resident Inspector Document Control Desk State of Georgia (
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ENCLOSURE 1 ENFORCEMENT CONFERENCE SUMMARY On October 21, 1987, an Enforcement Conference was held with representatives of Georgia Power Company (GPC) and the NRC.
The conference was held at the request of the NRC at the NRC, Region II Office located in Atlanta, Georgia.
The main topics of discussion were Technical Specification (TS) compliance regarding the Residual Heat Removal (RHR) System Alignment and failure to report all the events when the plant was in an unanalyzed condition.
Also discussed was prompt corrective action regarding IE Information Notice No. 87-01:
"RHR Valve Misalignment Causes Degradation of Emergency Core Cooling System (ECCS) in PWR 's."
GPC. positions regarding the proposed violations were presented during the conference and copies of viewgraphs which were used to support these positions are contained in Enclosure 2.
The information presented by GPC was basically their interpretation that adequate ECCS flow was availuble and that the plant operated within its design basis.
GPC was requested to present this new information justifying their position to perform surveillance testing of the RHR pumps and certain important RHR valves (8809 A & B and 8716 A & B) during plant conditions which appeared to be in conflict with IE Information Notice No. 87-01 and TS.
This information was submitted to the NRC by GPC in a letter dated October 27, 1987.
When the NRC staff completed their review of the October 27 GPC submittal, it was concluded in a letter to GPC dated November 5,1987, that the closure of the RHR Isolation Valves to Cold Legs (8809 A & B) in Mode 3 and the RHR Crossover Valves (8716 A & B) in Mode 1 is acceptable while performing the surveillance.
This acceptance was based on the determination that minimum ECCS flow requirements would be available.
As a further result of the enforcement conference the licensee submitted
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revision 1 to LER 87-55 on November 12, 1987.
This revision included the additional cases where the RHR lineup could affect flow.
This LER contains the corrective actions to preclude recurrence of this event.
Since both the licensee and NRC have reached additional understanding of the consequences of the event the LER could now be considered a voluntary submittal, however at the time of original submittal the licensee lacked the necessary information and should have concluded that the report was required.
Therefore, for the reasons stated above the proposed violations 50-424/87-56-01,
" Failure to Maintain the Residual Heat Removal System Operable per TS 3.5.2" and 50-424/87-56-02, " Failure to Adequately report the Residual Heat Removal
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System Inoperable Event" will not be issued and are administratively closed.
I R'egarding IE Information Notice No. 87-01, which was received at Plant Vogtle on January 12, 1987, the NRC has determined that prompt corrective action was not taken by GPC until approximately August 28, 1987, when a deficiency card was written.
This long delay in plant processing of the Information Notice j
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Enclosure 1 2'
was due to a breakdown in the plant administrative processing control system.
The result was that the significance of the Information Notice was not' realized
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for approximately seven months.
This constituted a violation in the failure to take prompt corrective action as required by 10 CFR part 50, Appendix B,Section XVI.
The NRC has determined.that this violation was identified and properly reported try the licensee and that corrective action to prevent. recurrence was taken.
Therefore, because the NRC wants to encourage and support licensee initiative I
for self-identification and correction of problems a notice of violation will not be issued.
This item is identified as LIV 875602 " Failure to Take Prompt Corrective Action In Response to an NRC Information Notice - LER 87-55."
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ENCLOSURE 2
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GPC/NRC ENFORCEMENT CONFERENCE
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OCTOBER 21, 1987-V0GTLE - 1 RHR SYSTEM VALVE ALIGNMENT AGENDA 1.
INTRODUCTION JAMES P. O'REILLY IL SYSTEM DESCRIPTION GEORGE B0CKHOLD III.
PLANT PROCESSING 0F IEN 87-01 GEORGE B0CKHOLD IV.
TECHNICAL SPECIFICATIONS UNDERSTANDING GEORGE BOCKHOLD
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V.
PLANT AND INDUSTRY EVENT ANALYSIS DAVID G. SMITH AND RESOLUTION PROGRAM VI.
SAFETY SIGNIFICANCE L.T. GUCYA VII.
CLOSING STATEMENT JAMES P. O'REILLY VIII.
NRC DISCUSSION
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RHR SURVEILLANCE OPERATIONS DATE 2-24-87 PUMP IST MODE 3 B VALVE 29 MIN., A VALVE 53 MIN.
3-9-87 REACTOR CRITICAL 3-18-87 RCS PRESSURE ISOL. (8809A, B) VALVES IST MODE 3 B VALVE 12 MIN., A VALVE 12 MIN.
4-3-87 VALVE STR0KE (8716A, B) IST MODE 1 B VALVE 3 MIN., A VALVE 3 MIN.
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4-16-87 PUMP IST MODE 1 B VALVE 39 MIN., A VALVE 46 MIN., TOTAL RWST 85 MIN.
7-3-87 VALVE STR0KE (8716A, B) IST MODE 1 B VALVE 3 MIN., A VALVE 3 MIN.
7-20-87 PUMP IST MODE 1 B VALVE 34 MIN., A VALVE 1 HR.12 MIN.
8-8-87 VALVE STROKE (8716A, B) IST MODE 1 B VALVE 3 MIN., A VALVE 3 MIN.
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3AN" PROCISS;:NG 07 3N 87-0:
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JANUARY 12 RECEIVED IEN 87-01
. JANUARY 28 OEP ISSUES IEN TO OPERATIONS FOR ACTION FEBRUARY 16++
OPERATIONS MANAGEMENT INFORMED IEN SHORT TERM CYCLING -. OK MARCH 11 WESTINGHOUSE LETTER RECEIVED MARCH 23 NSAC ISSUES WESTINGHOUSE LETTER FOR INF0 AUGUST 28 DEFICIENCY CARD WRITTEN NSAC CLASSIFIES AS SOR
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Xh::s];I';s C0: HIC"V:s AC"0NS
- FORMED CRITIQUE TEAM TO ANALYZE EVENT
- PLACED INFO TAGS ON HV-8809A & B AND HV-8716A &.B e REQUIRED REVIEW 0F IEN 87-01 BY LICENSED OPERATORS
- ISSUED ADMINISTRATIVE CONTROLS IF VALVES FOUND CLOSED e PREVIEWED OTHER TESTING FOR BROADNESS CONCERNS
- PLACED FLAGS IN NPMIS TO ENSURE SCREENING OF MW0'S ON VALVES IN MODES 1, 2, OR 3
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- MANAGEMENT ASSESSMENT EC5 I
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- ADD PRIORITY
- PRB INVOLVEMENT
- ENGINEERING INVOLVEMENT
- OPERATIONS OEP
DEFICIENCY CARD TRAINING 100% MWO AND CLEARANCE REVIEW SINCE REACTOR CRITICAL l
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INCREASED SENSITIVITY EMPHASIS
MANAGEMENT ACTION
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l T:BCE S?EC UNDERS"ANDNG-COEPLIANCE IMP ROV:BYEN"S
- STARTUP STAFF DEVELOPMENT EXPERIENCE HELPS IDENTIFY ISSUES TEAMWORK PRODUCES CORRECT RESOLUTION e CONSERVATIVE ACTION UNTIL RESOLUTION
- LESSONS LEARNED / IMPROVEMENT PROGRAM STRENGTHENED RESPONSE TIME SPECIAL REVIEWS SITE SPECIFIC INDUSTRY EVENTS
e OPERATIONAL STATUS MEETINGS
- ADDITIONAL SPECIAL TRAINING EC7
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FEBRUARY,1987 STRENGHTEN ORGANIZATION APRIL,1987 ESTABLISH ELECTRONIC FILE MAY,1987 EFFECTIVENESS REVIEWS AUGUST,1987 EXPAND EMPHASIS TO HATCH
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I REV EWS 0 NDUSTRY EVENTS
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BEGAN IN MAY WITH V0GTLE EMPHASIS
INITIAL V0GTLE EFFORT COMPLETED IN AUGUST l
l a) 179 RECOMMENDATIONS EXAMINED l
b) 630 MANHOURS INVESTED
ASSESSMENT METHODOLOGY:
a) ON-SITE INTERVIEWS b) ON-SITE OBSERVATIONS c) FIELD INSPECTIONS d) DOCUMENT CHECKS l
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SA?s"Y S::GN:TCANC:s AXJ.a.:CBXS::XG 3AS:sS
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RHR D.!SCHARGE VALVES (8809 A&B)
II.
RHR CROSSTIE VALVE STR0 KING (8716 A&B)
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III.
RHR PUMP TESTING l
ADEQUATE ECCS FLOW AVAILABIE
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- R:-:1 ISCHIRG3 VA1VIS (8809 A&3)
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- EACH VALVE CLOSED FOR ABOUT 12 MINUTES IN MODE 3
- OPERABILITY CONSIDERATIONS ARE BASED ON MODE 1 OPERATION
- ECCS FLOW AVAILABLE EXCEEDED REQUIREMENTS FOR MODE 3
- ANALYSIS SHOWS SMALL INCREASE IN SYSTEM UNAVAILABILITY FOR CLOSURE OF VALVES PLANT OPERATED
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RHR CROSSTIE VALVE STROKING (8716 A&B)
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STROKE TESTED EVERY 90 DAYS PER ASME SECTION XI
- APPR0XIMATE TIME CLOSED IS THREE MINUTES
STR0KE TESTS CONDUCTED IN MODE 1 ANALYSIS SHOWS THAT CLOSURE OF CROSSTIE VALVES HAS IJ1TLE
EFFECT ON SYSTEM UNAVAILABILITY (ESS THAN THE EFFECT ON SYSTEM UNAVAILABILITY DUE TO PUMP MAINTENANCE)
- ASSURES AVAILABILITY OF HOT EG RECIRCULATION POST-LOCA
- VALVE STROKING IS WITHIN DESIGN BASIS
'1 PERI 0b10 STR0KE TESTING 0F 8716 A&B ACCEPTABLE AND DESIRABE TO ASSURE VALVE REIJABIIJTY EC10 L___--_-___--_-__-_
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RER PUMP TESTING
PUMPS ARE FLOW TESTED EVERY 90 DAYS PER ASME SECTION XI
PUMP FLOW TESTS CONDUCTED ON THREE OCCASIONS
RECIRCULATING FLOW TO RWST WITHOUT CLOSING VALVES 8809 A (0R B) PERMITS PARTIAL FLOW TO RCS IN CASE OF LOCA
ECCS FLOW AVAILABLE EXCEEDED MINIMUM FLOW ASSUMED FOR LOCA
- ANALYSIS SHOWS SMALL INCREASE IN SYSTEM UNAVAILABILITY FOR CLOSURE OF VALVES TWO HOURS EVERY THREE MONTHS
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PUMP FLOW TESTING IN MODES 1, 2, OR 3 IS ACCEPTABLE
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ENCLOSURE 3 i
LIST OF' ATTENDEES NRC, Region II J. N. Grace, Regional Administrator
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A. F. Gibson, Director, Division of Reactor Safety V. L. Brownlee', Acting Deputy Director, Division of Reactor Projects (DRP)
l M. V. Sinkule, Chief, Section 20, DRP
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B. Uryc, Enforcement Coordinator, EICS J.~F. Rogge, Senior Resident Inspector for Operations, Section 20. DRP-C. Burger, Resident Inspector - Operations, Section 2C, DRP R. Schepens, Resident Inspector - Operations, Section 2C, DRP L. Trocine, Enforcement Specialist, EICS I
P. A. Balmain, Acting Project Engineer, Section 2C, DRP NRC Headquarters W. M.-Troskoski, Regional Coordinator, DEDR0 M. Miller, Vogtle Project Manager, Project Directorate II - 3, NRR
Georgia Power Company, (GPC)
J. P. O'Reilly, Senior Vice President - Nuclear Operation G. Bockhold, General Manager, Nuclear Operation, Vogtle j
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J. Swartzwelder, Manager, Nuclear Safety and Compliance
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R. Baker, Manager, Nuclear Licensing
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L. T. Gucwa, Manager Nuclear Safety and Licensing D. Smith, Manager, Nuclear Performance and Rad. Safety C. Eckert, Technical Assistant to Plant Manager
J. Puckett, Assistant to Manager, Nuclear Safety and Licensing i
W. Gabbard, Senior Regulatory Specialist
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Westinghouse Electric Company (WEC)
M. Hitchler, Manager, Plant Risk Analysis E. Burns, Licensing
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