ML20236G534

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Summary of 870701 Enforcement Conference at Plant Re Three Violations Noted in Insp Repts 50-424/87-31 & 50-425/87-37. Violations Concern Tech Spec Compliances Pertaining to RHR & Reactor Trip Breaker.List of Attendees & Viewgraphs Encl
ML20236G534
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 07/27/1987
From: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: James O'Reilly
GEORGIA POWER CO.
References
NUDOCS 8708040300
Download: ML20236G534 (26)


See also: IR 05000424/1987031

Text

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JUL 2 71987

Docket No. 50-424

License No. NPF-68

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Georgia Power Company

t, ATTN: Mr. James P. O'Reilly

Senior Vice President-

Nuclear Operations

P. O. Box 4545

Atlanta, GA 30302

Gentlemen:

SUBJECT: ENFORCEMENT CONFERENCE SUMMARY - REPORT NO. 50-424/87-45  ;

This letter refers to the Enforcement Conference conducted, at our request, at

the Vogtle site on July 1, 1987. This meeting concerned three potential

violations described in NRC Inspection Report Nos. 50-424/87-31 and )

50-425/87-37. These violations represented Technical Specification 1

compliances regarding residual heat removal operability, reactor trip breaker

operability, and diesel generator operability, i

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Our concerns were expressed to you at the meeting and your positive response to

our concerns was appreciated.

It is our opinion that this meeting was beneficial and has provided for a

better mutual understanding of the inspection findings and enforcement issues. -

We also found your description of the findings and your corrective actions to

be beneficial in our evaluation of the issues. In accordance with Section ]

2.790 of NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regula- i

tions, a copy of this letter and the enclosures will be placed in NRC's Public

Document Room.

Should you have any questions concerning this letter, please contact this

office.  ;

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Sincerely,

Original Signed by 1

M. L. Ernst/for i

J. Nelson Grace

Regional Administrator

Enclosures: (See E. Christnot)

1. Enforcement Conference Summary

2. Enforcement Conference Technical

Specification Compliance

3. List of Attendees

(cc w/encis: See page 2)

8040300 870727

G ADOCK 05000424 g

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Georgia Power Company 2  !

JUL 2 71987 l

cc w/encis: I

f D. Rice, Vice President, Project )

Director

LC< W. Hayes, Vogtle Quality

Assurance Manager i

g Bockhold, Jr. , General Manager, J

Nuclear Operations

W. Gucwa, Manager, Nuclear Safety

and Licensing

A. Bailey, Project Licensing

g(Manager )

y W. Churchill, Esq., Shaw, l

fittman,PottsandTrowbridge  ;

tJ. E. Joiner, Troutman, Sanders, 4

tp.fockermanandAshmore

,

Kirkland, III, Counsel,  !

Office of the Consumer's Utility J

Council

LU,. Feig, Georgians Against

Nuclear Energy

L)if B. Margulies, Esq. , Chairman,

Atomic Safety and Licensing Board

Panel

LDr' O. H. Paris, Administrative Judge

Atomic Safety and Licensing Board

Panel

LG A. Linenberger, Jr. , Administrative Judge

Atomic Safety and Licensing Board

Panel

bec w/encis:

LE'.' Reis, OGC

LM'. Miller, NRR

M.,Sinkule, RII i

LNRC Resident Inspector I

Document Control Desk

State of Georgia

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EChristnot:9Em MSinkule VLBrownlee , Reyes

07/2V86 07/ g/86 07/jg/.86 07pN86 13

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ENCLOSURE 1 4

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ENFORCEMENT CONFERENCE SUMMARY  !

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On July 1,1987, representatives of Georgia Power Company (GPC) met with the l

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NRC at the NRC's request at the Vogtle site near Waynesboro, Georgia. The main 1

topics of discussion were Technical Specification (TS) compliance regarding the

residual heat removal (RHR) operability, reactor trip breaker (RTB) operabi-  !

lity, and the Trans Delaval Inc. (TDI) diesel generator (DG) operability. j

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GPC positions regarding these violations are presented in Enclosure 2. The j

security issue addressed in this Enclosure will be discussed in separate j

correspondence. l

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The information presented by GPC basically confirmed the violations regarding

the RHR and RTB compliance. New information on how GPC interprets the DG

license condition and TS Action Statements was received. Since NRC represen-

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tatives consider your approach to be a conservative interpretation, the

Violation as indicated as 50-424/87-37-03 " Failure to Follow TS 3.8.1.1 Actions .

Regarding the Activities Which Render the Diesel Inoperable" is closed and i

Unresolved Item 50-424/87-45-01 " Resolve License Condition and DG Action

Statement Compliance" is open. The purpose for the Unresolved Item will allow

the staff to determine the appropriate course of action. The current staff

position is that footnotes are part of the Action Statement and since one i

footnote requires the test to be completed regardless of when the diesel is

returned to service, the licensee remains in the Action Statement while in full

compliance with the LCO. The second footnote then requires that the diesel not

be rendered inoperable when pursuant to the Action Statement. Your position

being that, while one footnote requires a test only after full LCO compliance j

is achieved, this is not part of the Action Statement and thus the second q

footnote does not apply to the diesel. The NRC, when developing the TDI TS, '

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however did not consider your approach.

Regarding the RTB, the NRC disagrees with your position that you were in

compliance with Action 13 of TS 3.3.1. We also note that your interpretat on

provided to the Shift Personnel limits the time-to perform maintenance to less

than two hours until the issue is resolved. Action to resolve the issue rests

soley with your corporate and site organization issuing the correct clarifica-

tion. Since the event occurred on June 2 and the interim interpretation was

not issued until June 21, the NRC is concerned with your staff's ability to

achieve prompt corrective action to prevent recurrence.

The NRC is presently considering enforcement action of the RHR and RTB issues.

This meeting served to enhance Region II's understanding of the issues.  !

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ENCLOSURE 2 4

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NUCLEAR RE6ULATORY COPfilSSION 1

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ENFORCEMENT CONFERENCE 1

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TECHNICAL SPECIFICATION COMPLIANCE

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JULY L 1987

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AGENDA

OPENING REMARKS................................J. P. O'REILLY

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RHR VALVES.....................................T. V. GREENE, JR.

DIESEL GENERATOR TEST..........................L. T. GUCWA

REACTOR TRIP BREAKER...........................L. T. GUCWA

SECURITY ACCESS..... ..........................M. P. CRAVEN

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l PROGRAMMATIC ASSESSMENT........................G. B0CKHOLD, JR. i

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CLOSING REMARKS................................J. P. O'REILLY

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RHR VALVE POSITION

O PROPOSED VIOLATION

FAILURE TO DECLARE BOTH RHR TRAINS INOPERABLE AND COMPLY

WITH TECHNICAL SPECIFICATION:3.5.2.

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RHR VALVE POSITION - CONTINUED

0 CHRONOLOGY

APRIL 28, 1987

0 1345 ENGINEER NOTICED AIR PRESSURE ON VALVES

ESTIMATED POSITION 90 - 95% OF FULL OPEN

0 1411 SHIFT SUPERVISOR NOTIFIED, DEFICIENCY CARD

WRITTEN

0 1500 OSOS DECISION - OPERABLE BASED ON

TECH. SPEC. SURVEILLANCE STATUS AND MAIN

CONTROL ROOM INDICATIONS. OSOS CONTINUED i

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REVIEW 0F TECH. SPEC., FSAR, VENDOR PRINTS,

CRANE VALVE MANUAL, AND DISCUSSIONS WITH

ENGINEERING; CONFIRMS "0PERAELE" DECISION.

0 1658 MWO IN WORK PLANNING

APRIL 29, 1987

0

DEFICIENCY CARD TO ENGINEERING

0 2000 MWO COMPLETE

MAY 14, 1987 i

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DETAIL ENGINEERING REVIEW COMPLETE

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RHR VALVE POSITION - CONTINUED

0 APPLICABLE REFERENCES

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0 TECHNICAL SPECIFICATIONS 3.5.2

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O TECHNICAL SPECIFICATIONS 3.0.3

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RHR VALVE POSITION - CONTINUED

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0 ENGINEERING REVIEW

0 BASED ON STARTUP TEST DATA

0 TECH. SPEC. FLOW - 3788 GPM

o CALCULATED FLOW

- AT 90% 0.7 TO 2.7% BELOW 3788

- AT 92.5% > 3788

__

0 CALCULATED POSITION FOR 3788 GPM

- TRAIN A 91% i

- TRAIN B 92.5%

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RHR VALVE POSITION - CONTINUED

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O DISCUSSION

0 ALL SURVEILLANCE SATISFACTORY

0 CONTROL ROOM INDICATIONS NORMAL

0 NO POSITION INDICATION ON VALVE

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o ENGINEER ESTIMATED POSITION

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90 - 95% OPEN

- FELT TIP MARKS ON STEM

- POSITIONER CAM j

0

VALVE THROTTLED FOR PUMP PROTECTION

0

N0 VALVE MAIN 1ENANCE SINCE PREVIOUS SATISFACTORY

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SURVEILLANCE  !

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RHR VALVE POSITION - CONTINUED

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0 CONCLUSIONS .

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NON CONSERVATIVE SYSTEM EVALUATION BY ON SHIFT MANAGEMENT

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SUBSEQUENT INVESTIGATION INCONCLUSIVE

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FLOW MAY HAVE BEEN BELOW TECH. SPEC.

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MARGINAL DEVIATION IF AT ALL

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RHR VALVE POSITION - CONTINUED

IMPROVEMENT ACTIONS

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0 CALIBRATION FREQUENCY

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WAS 24 MONTHS

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NOW 6 MONTHS

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CLARIFICATION OF OPERABILITY DETERMINATION

0 SHIFT PERSONNEL BRIEFED BY PLANT MANAGER

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DIESEL GENERATOR

0 ISSUE

PERFORMANCE OF TEST ON DIESEL GENERATOR PER LICENSE

REQUIREMENTS INSTEAD OF THE APPLICABLE TECHNICAL

SPECIFICATION REQUIREMENTS.

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DIESEL GENERATOR - CONTINUED

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O CHRONOLOGY

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JUNE 15, 1987

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O BOTH DIESELS OPERABLE

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o 0321 D/6 IB DECLARED INOPERABLE TO

CHAN6E SEQUENCER TEST CARD

LCO INITIATED PER TECH. SPEC. 3.8.1.1

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0FFSITE SOURCE VERIFICATION COMPLETED

o 0331 SEQUENCER MAINTENANCE-COMPLETE 1

LC0 CLEARED

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BOTH DIESELS OPERABLE

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0 1650 D/6 1A STARTED FOR SURVEILLANCE

MOISTURE CHECK PER LICENSE

o 183'4 D/6 1A STOPPED

-BOTH DIESELS OPERABLE

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DIESEL GENERATOR - CONTINUED

o APPLICABLE REFERENCES

0 TECH. SPEC. 3/4.8.1 b,

... PERFORM SURVEILLANCE REQUIREENT

4.8.1.1.2. . 4 AND 4.8.1.1.2. a.5 WITHlW 24 HOURS * #.

NOTE *

THIS TEST IS REQUIRED TO BE COPPLETED REGARDLESS OF WHEN

TE INOPERABLE DIESEL GENERATOR IS RESTORED TO OPERABILITY

NOTE #

TE DIESEL SHALL NOT BE RENDERED INOPERABLE BY ACTIVITIE

PERFORED TO SUPPORT TESTING PURSUANT TO THE ACTION STATE-

ENT (e.g., AN AIR ROLL).

O TECH. SPEC. 3.0.2

...IF TE LIMITING CONDITION FOR OPERATION IS RESTORED

PRIOR TO EXPIRATION OF TE SPECIFIED TIE INTERVALS,

C0fFLETION OF THE ACTION STATEENT IS NOT REQUIRED

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DIESEL GENERATOR - CONTINUED

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0 DISCUSSION

0 NOTES ARE SEPARATED AND THEREFORE ALLOWS NOTE # TO BE

NOT APPLICABLE WHEN SECOND D/G IS MADE OPERABLE. '

O NOTE # NOT APPLICABLE TO TEST DUE TO TECH. SPEC. 3.0.2

0 IF INTENDED TO USE BOTH NOTES SIMULTANEOUSLY THERE

WOULD ONLY HAVE BEEN ONE NOTE.  ;

o FIRST APPLICATION OF THIS TECH. SPEC.

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O CONCLUSIONS

0 BOTH D/G OPERABLE PRIOR TO CONDUCTING SURVEILLANCE

o ACTIONS IN COMPLIANCE WITH TECHNICAL SPECIFICATIONS

o ACTIONS REQUIRED BY LICENSE

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REACTOR TRIP BREAKERS

0 ISSUE

SCRAM BREAKER INOPERABLE WITH THE BYPASS SCRAM BREAKER

CLOSED IN EXCESS OF SIX (6) HOURS AS ALLOWED IN TECHNICAL

SPECIFICATIONS.

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REACTOR TRIP BREAKERS - CONTINUED

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0 CHRON0 LOGY 6/2/87 l

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0 1003 HRS RTB SURVEILLANCE INITIATES I

I o 1100 HRS ENTERED LC0 1-87-554 ON RTB "B" DUE TO AUTO  !

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SHUNT TRIP FEATURE j

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REACTOR TRIP. BYPASS BREAKER "B" OPENED l

l 0 1214 HRS RTBB "B" CLOSED TO COMENCE WORK PER

MWO 1-87-06672

0 2048 HRS RTBB "B" 0PENED

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0 2114 HRS COMENCED OSP 14701-1 SURVEILLANCE l

0 2200 HRS OSP 14701-1 FOR RTB COMPLETE

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1 CLEARED LCO 1-87-554  ;

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REACTOR TRIP BREAKERS - CONTINUED

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O DISCUSSION )

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o ACTION STATEENT 13 ALLOWS RTB TO BE OPERABLE WITH ONE

DIVERSE TRIP FEATURE IN0PERABLE FOR 48 HOURS.

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ACTION STATEENT 13 ALLOWS THE RTB TO BE BYPASSED WHILE

MAINTENANCE IS BEING PERFORED.

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ACTION STATEENT 10 REQUIRES THE PLANT TO 60 TO HOT STANDBY

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ACTION STATEENT 10 PERMITS BYPASSING A RTB FOR UP TO TWO '

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0 TECH. SPEC, 3.3.1 - TABLE 3.3.1

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REACTOR TRIP BREAKERS - CONTINUED i

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0 CONCLUSIONS

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ACTIONS IN COMPLIANCE WITH ACTION STATEMENT 13

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ACTION STATEMENT 10 APPLICABILITY UNCLEAR FOR THIS

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TRIP RELIABILITY WAS REDUCED WITH THE BYPASS BREAKER

CLOSED WHILE PERFORMING MAINTENANCE

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REACTOR TRIP BREAKERS - CONTINUED

V0GTLE ACTIONS

0 AN INTERIM TECH. SPEC. INTERPRETATION WAS WRITTEN LIMITING

BYPASS BREAKER CLOSED T0 lWO HOURS.

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ENCLOSURE 3

LIST OF ATTENDEES

NRC, Region II

J. N. Grace, Regional Administrator

A. F. Gibson, Director, Division of Reactor Safety

L. A. Reyes, Director, Division of Reactor Projects (DRP)

G. R. Jenkins, Director, Enforcement and Investigation Coordination Staff

W. E. Cline, Chief, Nuclear Material Safety and Safeguards Branch, Division of

Radiation Safety and Safeguards (DRSS)

M. V. Sinkule, Chief, Section 2C, DRP

J. F. Rogge, Senior Resident Inspector for Operations, Section 2C, DRP

NRC, Headquarters

W. Troskoski, Regulatory Coordinator, DEDRO

Georgia Power Company, (GPC)

J. P. O'Reilly, Senior Vice President - Nuclear Operations

G. Bockhold, General Manager, Vogtle

T. Greene, Plant Manager, Vogtle

E. M. Howard, Manager Nuclear Training, Emergency Preparedness and Security

L. T. Gucwa, Manager Nuclear Safety and Licensing

P. R. Bemis, Manager Plant Support, Vogtle

A. Domby, GPC Legal Representative (Troutman Sanders)

W. E. Burns, Manager Nuclear Licensing

J. E. Swartzwelder, Deputy Manager Operations - Vogtle

D. Smith, Superintendent Nuclear Operations - Vogtle

R. M. Odom, Supervisor Engineering, NSAC

E. M. Danemiller, Technical Assistant to General Manager - Vogtle

Southern Company Services

D. Dutton, Vice President - Nuclear

R. L. George, Manager, NPSD

R. Thomas, Executive Consultant