ML20151S704

Summary of 880412 Meeting W/Util in Atlanta,Ga,To Discuss Status of Licensing Issues.List of Attendees,Agenda,Status of TACs & Proposed Tech Specs Encl

ML20151S704
Person / Time
Site:	Summer
Issue date:	04/22/1988
From:	Hayes J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8804280426
Download: ML20151S704 (15)

Text

. ,

ES' Docket No.'50-395 01STRIBUTION See attached sheet LICENSEE: South Carolina Electric'and Gas Company FACILITY: V. C. Sumer Nuclear Station 5UBJECT:

SUMMARY

OF MEETING WITH SOUTH CAROLINA ELECTRIC AND GAS COMPANY.

General On April 12, 1988, the NRC staff, consisting of representatives of the Office of Nuclear Reactor Regulation, Region II, and the V. C. Sumer Senior Resident Inspector, met with the South Carolina Electric and Gas Company (SCE&G) to discuss the status of licensing issues for the V. C. Sumer Station. The meeting was held at the Region II Headquarters in Atlanta, Ga. A list of those persons who attended the meeting is included os Enclosure 1.

Discussion The agenda for the meeting is included as Enclosure 2. A handout was provided at the meeting which provided the NRC's current assessment of the status of various licensing actions. This handout is included as Enclosure 3. During the discussion of Enclosure 3 it was noted that SCE&G had provided their response to NRC Bulletin 88-01 (TAC 65955/56) on March 30, 1988 and their response to NRC Eulletin 88-02 on March 24, 1988. Also, it was noted that the ISI relief request (TAC 67812) does not require a Sholly Notice. SCE&G also provided a draft of a letter and a revision to their technical specifications (TS) request to delete the organizational charts from the TS. This draft was provided for discussion purposes and was provided as a result of the recent issuance of Generic Letter 88 06, "REMOVAL OF ORGANIZATION CHARTS FROM TECHNICAL SPECIFICATION ADMINISTRATIVE CONTROL REQUIREMENTS." This draft is included as Enclosure 4.

The next meeting is currently scheduled for June 28, 1988 at the V. C. Sumer Station in Jenkinsville, SC.

\b\

John J. Hayes, Jr., Project Manager Project Directorate 11-1 Division of Reactor Projects I/II

Enclosures:

As stated cc: See next page 0FFICIAL RECORD COPY  :

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DATE : 4/ /88  : 4/1//88  : 4/()'/88  :  :  :  :

8804280426 880422 PDR ADOCK 05000395 p PDR

\ , ,/

/ o,, UNITED STATES

! n - NUCLEAR REGULATORY COMMISSION

$ WASHINGTON, D. C. 20555

\*****/ APR 2 21988 Docket No. 50-395 LICENSEE: South Carolina Electric and Gas Company FACILITY: V. C. Sumer Nuclear Station

SUMMARY

OF MEETING WITH SOUTH CAROLINA ELECTRIC AND GAS COMPANY General On April 12, 1988, the NRC staff, consisting of representatives of the Office of Nuclear Reactor Regulation, Region II, and the V. C. Summer Senior Resident Inspector, met with the South Carolina Electric and Gas Company (SCE&G) to discuss the status of licensing issues for the V. C. Sumer Station. The meeting was held at the Region II Headquarters in Atlanta, Ga. A list of those persons who attended the meeting is included as Enclosure 1.

Discussion The agenda for the meeting is included as Enclosure 2. A handout was provided at the meeting which provided the NRC's current assessment of the status of various licensing actions. This handout is included as Enclosure 3. During the discussion of Enclosure 3 it was noted that SCE&G had provided their response to NRC Bulletin 88-01 (TAC 65955/56) on March 30, 1988 and their response to NRC Bulletin 88-02 on March 24, 1988. Also, it was noted that the ISI relief request (TAC 67812) does not require a Sholly Notice. SCE&G also provided a draft of a letter and a revision to their technical specifications (TS) request to delete the organizational charts from the TS. This draft was provided for discussion purposes and was provided as a result of the recent issuance of Generic Letter 88-06, "REMOVAL OF ORGANIZATION CHARTS FROM TECHNICAL SPECIFICATION ADMINISTRATIVE CONTROL REQUIREMENTS." This draft is included as Enclosure 4.

The next meeting is currently scheduled for June 28, 1988 at the V. C. Summer Station in Jenkinsville, SC.

M 4 J ' n J. HJyes, Jr# Project Manager Project Directorate 11-1 Division of Reactor Projects 1/II

Enclosures:

As stated cc: See next page

Mr. D. A. Nauman South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station cc:

Mr. William A. Williams, Jr.

Technical Assistant - Nuclear Operations Santee Cooper P.O. Box 764 (Mail Code 153)

Columbia, South Carolina 29218 J. B. Knotts, Jr. , Esq.

Bishop, Cook, Purcell and Reynolds 1400 L Street, N.W.

Washington, D. C. 20005-3502 Resident Inspector / Summer NPS c/o U.S. Nuclear Regulatory Commission Route 1, Box 64 Jenkinsville, South Carolina 29065 Regional Administrator, Region II U.S. Nuclear Regulatory Commission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Chairman, Fairfield County Council P.O. Box 293 Winnsboro South Carolina 29180 Attorney General Box 11549 Columbia, South Carolina 29211 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201

r:.. . .

t I A y ENCLOSURE 1 ATTENDANCE -

' APRIL 12, 1988 MEETING SCE&G NRC-

' N.. Williams H. Dance

- A. Koon, Jr. R.'Prevatte J. Hayes, Jr.

, ENCLOSURE 2 AGENDA NRC MEETING WITH SCE&G APRIL 12, 1988 TUESDAY ,0APRILQ12. 01988

1. STATUS OF LICENSING ACTIONS 11:00A

2. TECHNICAL SPECIFICATION CHANGES IN 12:00A PROGRESS /OTHER LICENSING ACTIONS 1

fg~-

' ENCLOSURE 3 l

h STATUS OF NRC TACS FOR THE V.-C.-SUMMER PLANT ,

APRIL 11. 1988 '

r 40970 ISI/IST0 PROGRAMS IST (KEN-DEMPSEY) ['

-SER TO BE ISSUED DURING '4/88

-SOME RELIEFS DENIED, SOME GRANTED

-LICENSEE MUST ADDRESS APPENDIX C OF THE TER WHICH '

COVERS OMISSIONS AND INCONSISTENCIES IN THE PROGRAM. I ISI (MARTIN HUME)

I

-REVIEWER PROMISES SE BY 6/88'.

51137 RG01.970 INSTRUMENTATION (BARRY MARCUS)

-SER ISSUED .

-THREE OPEN ITEMS  !

- ONE FOR STAFF ACTION 1

-generic review of the need for Cat 2 EQ instrumentation to monitor accumulator pressure and temperature.

- TWO FOR SCE&G ACTION (MORE INFORMATION) '!

-install instrumentation to monitor containment temperature between 40-400 F  !'

or provide an analysis justifying the use of the 50-350 F irstrumentation.

i

-have operational EQ instrumentation to monitor SG SRVs and ADVs releaccc.  ;

- LICENSEE SUBMITTED RESPONSE DATED 2/16/88  !

JUSTIFYING THEIR POSITION ON THE TWO SCE&G '

ITEMS.

-TER ACCEPTS BOTH JUSTIFICATIONS.

-REVIEWEP TO ISSUE SE 5/88 TO PM.

51287 SPDS (S. SABA, G. LAPINSKY) .

-SER ISSUED

-THREE OPEN ITEMS

i. 1. TOP LEVEL ICONICS ARE NOT CONTINUOUSLY '

DISPLAYED.

i

2.  ;

a. SYSTEM RESPONSE TO OPERATOR COMMANDS IS l VERY SLOW.

l b. SYSTEM HAS NOT BEEN ABLE TO MEET ITS  !

i UNAVAILABILITY GOAL OF LESS THAN 1 %.

c, LACK OF REDUNDANCY IN THA DATA ACQUISITION CONTROLLER AND THE UNIBAR i  !

l  ;

I

s CONTROL SWITCH INCREASES THE VUL?lERABILITY OF THE SYSTEM TO FAILURES CAUSED BY THESE COMPONENTS.

3. HUMAN FACTOR PRINCIPALS NEED TO BE RESOLVED.

4. SOME NON-VALID VALUES OR CONDITIONAL FLAGS EXISTED FOR RHR FLOW RATE, SUBCOOLING MARGIN, REACTOR VESSEL LEVEL INDICATTION SYSTEM (RVLIS), STARTUP RATE, CONTAINMENT HYDROGEN, AND SAFETY INJECTION (SI) FLOW.

-RESPONSE DUE FROM THE LICENSEE.

51606 RV0ANDOSVOTESTING0(II.D.11 (GARY HAMMER)

-SCE&G OWES STAFF RESPONSE.

-RESPONSE DUE FROM THE LICENSEE EARLY APRIL.

53406 AUT00SHUNTOTRIPOTS.0GLO83-280 ITEM 4.3 (DON LASHER)

-RAI ISSUED.

-CLARIFICATION

-THAT TS TABLE 4.3-1 FUNCTIONAL UNIT NO. 1 "MANUAL REACTOR TRIP" APPLIES TO RT BYPASS BREAKERS AS WELL AS RT BREAKERS.

-TS TABLE 4.3-1 NOTATION 13 DOES NOT COMPLY WITH THE GL WHICH SPECIFIES AN AUTOMATIC UNDERVOLTAGE TRIP.

-RESPONSE DUE FROM THE LICENSEE.

53720 ITEM 02 200FOGLO83-28.0EOUIP.0 CLASSIFICATION 0AND VENDOR 0 INTERFACE 0FOROSAFETYORELATED0 COMPONENTS (DON LASHER)

-FARLEY TO BE HANDLED AS THE LEAD PLANT

-TER ISSUED BY EG&G

-OPEN ITEMS ARE:

-CONTACT VENDORS OF KEY COMPONENTS SUCH AS AFW PUMPS, ECCS PUMPS SAFETY RELATED BATTERIES, AND SAFETY RELATED VALVES TO FACILITATE THE EXCHANGE OF CURRENT TECHNICAL INFORMATION.

AN INFORMAL INTERFACE AGREEMENT SHOULD BE ESTABLISHED.

-FOR DGs AND SAFETY RELATED SWITCHGEAR VENDORS A FORMAL INTERFACE SIMILAR TO THAT WITH THE NSSS SHOULD BE ESTABLISHED.

-REVIEWER TO PROVIDE THE STATUS DURING APRIL.

53942 I TEMSO4 . 2. 30&O4 . 2 . 400F0G LO 83 - 2 8 . 0PREVENILVJ MAlllTlBANCE0 PROGRAM ERRQHKOTRIP0 BREAKERS.0 LIFE TESTING 0&OREPLACEMENI (N. ROMNEY)

-AWAITING ISSUANCE OF A GENERIC LETTER BY MANAGEMENT TO ADDRESS THESE ITEMS.

54030 ITEMSO4.5.20&O4.5.300FOGLO83-28.0 REACTOR 0 TRIP SLS_ TEM 0 FUNCTIONAL TESTING 0 ALTERNATIVES 0&OTEST INTERVALS (N. ROMNEY)

-4,5.2 COMPLETED.

-AWAITING INPUT FROM OWNERS GROUP TO ADDRESS 4.5.3.

55344 PROCEDURES 0 GENERATION 0 PACKAGES 0(SUPPLEMENT 01.

NUREG-00737) (GEORGE LAPINSKY)

-DRAFT SE ISSUED 6/29/87.

-PROBLEMS IDENTIFIED INCLUDED:

1. PLANT SPECIFIC TECHNICAL GUIDELINES.

2. WRITERS GUIDE.

3. PROGRAM USED FOR VALIDATION OF E0Ps.

4. TRAINING PROGRAM FOR UPGRADED EOPs.

-SCE&G ORES RESPONSE TO THE STAFF COMMENTS.

56169 .TMI0 ACTION 0ITEMOI.D.1.2.0 DETAILED 0CONTROLOR00M LSSIGNOREVIEWO

SUMMARY

OREPORT (GEORGE LAPINSKY)

-NEGATIVE SER ISSUED.

-NEW REPORT ISSUED BY LICENSEE 5/28/87.

-CONFERENCE CALL HELD TO CLARIFY REVIEWERS QUESTIONS.

-SE TO BE ISSUED TO PM 4/88.

56935 RCPOTRIP0 CRITERIA.0GLO83-10D (S. L. WU)

-REVIEW RETURNED FROM THE REGION.

-PM TO HOLD DISCUSSION WITH THE REVIEWER.

59146 10CFR50.6200PERATINGOREACTORSOREVIEWOATWS (R.

STEVENS)

-SUBMITTAL MADE BY THE LICENSEE 3/24/88.

-CONTRACTOR TO COMPLETE REVIEW BY THE END OF 5/88.

-CONFERENCE CALL TO BE HELD 4/20/88; 10:00 AM.

594C2 400 YEAR 00LOLIFE0AMENDMEtLT

-LICENSEE RESPONDED 3/30/88.

NEW REVIEWER TO BE ASSIGNED DUE TO PROMOTION OF THE PREVIOUS REVIEWER.

59451 DIESEL 0 GENERATORS 0TS

-REQUEST FOR ADDITIONAL INFORMATION SUBMITTED TO SCE&G 11/9/87.

-COMMENTS ON 11/0/87 LETTER DEALT WITH TS 3/4.3.1.1 AND 4.8.1.2.

c - .

? 4' r

6 82803 -CQHIAINMENT0 STRUCTURE 0 INTEGRITY (C. P.' TAN)

-LICENSEE REPONSE SENT 3/17/88.

-NRC REVIEW TO BE COMPLETED 4/15/88.

64558 RB0 COOLING 0 SYSTEM s

-AMENDMENT PACKAGE IN CONCURRENCE CHAIN.  :

64821 RSB05-1.0 NATURAL 0 CIRCULATION 0TESTOOFOTHE0 REACTOR COOLANT  ;

-CHECK AS WHO HAS THIS ITEM IN THE NEW r ORGANIZATION.  !

-SCE&G MUST MEET LICENSEE CONDITION. .  ;

65060 EEMOVALOOF0 FIRE 0 PROTECTION 0REQUIREMENTSOFROMOTHE0TS -

GLO86-10 5

-RE-SHOLLY ISSUED 2/24/88.

-AMENDMENT TO BE ISSUED 5/88.

65321 EHYSICALOSECURITYOPLAN 5

-SHOLLIED 3/23/88. '

-SE TO BE ISSUED 5/88.

65778 REMOVALOOFOORGANIZATIONALOCHARTSOFROMOTHEOTS t

-SCE&G OWES INPUT BASED UPON GL 88-06.

65779 FISSION 0 CHAMBER 0 DETECTORS

-REGION II TO PROVIDE PM SE 5/88. .

65955/56 DEFECTS 0IN0 WESTINGHOUSE 0CIRCUITOBREAKERS 0 BULLETIN 88-01

-REPORT DUE WITHIN 30 DAYS OF THE COMPLETION OF THE SHORT TERM AND LONG TERM INSPECTIONS.

-LICENSEE REPORT DUE 4/88.

66258 LOSS 00FORHROWHILEORCSOPARTIALLYOFILLED.01/20 LOOP OPERATION

-COPIES OF SCE&G SUBMITTAL SENT TO LEAD PM AND LEAD REVIEWER.

67077 SERVICE 0WATEROPUMPOROOMOTEMPERATURE0 MONITORING 0TS 3.7.1.1

-SHOLLEY NOTICE ISSUED 2/24/88.

-SE TO BE ISSUED 5/88.

67279 STEAMOBISDING00FOAFWOPCMPS.0GLO88-03.0MPAOB-98

-LICENSEE RESPONSE DUE 5/17/88.

67327 RAPIDLY 0 PROPAGATING 0 FATIGUE 0CRACKSOINOSGOTUBES.

BULLETIN 088-00

-LICENSEE RESPONSE DUE 3/21/88.

67339 TS0 AMENDMENT 0TOOSECTION0600NONSRC0 ADDITION 00F0 EXEC.

ZE

-SHOLLIED 3/23/88.

-AMENDMENT TO BE ISSUED 5/88.

67340 ORGANIZATIONAL 0 CHARTS 0TOOREFLECT01/25/88 REORGANIZA RQE

-WILL NOT BE PROCESSED DUE TO THE PROCESSING OF TAC 65778.

67811 VANTAGE 050 FUEL.0FUELOSTORAGE

-TO BE SHOLLIED.

67812 ISIORELIEF.0HYDP,QSTATICOTESTINGOOFOTHEOSGBOSYSTEM

-TO BE SHOLLIED.

????? BORIC 0 ACID 0 CORROSION 00FOC-STEELOCOMPONENTS0INOPWR PLANTSOGLO88-05

-LICENSEE RESPONSE DUE 5/17/88.

l

, . . ENCLOSURE 4 April 28, 1988 .

Document Control Oesk U. S. Nuclear Regula. tory Comission Washington, OC 20555 Attention: Mr. J. J. Hayes, Jr.

Subject:

Virgil C. Sumer Nuclear Station Document No. 5/395 Operating License No. NPF-12 Technical Specifications Deletion of Organization Charts and Revision of Training Requirements Gentlemen:

As discussed during a telephone conversation on April 7, 1988, the attached Virgil C. Summer Nuclear Station Technical Specifications pages 6.1 and 6.2 have been amended to reflect additional information added as a result of Generic Letter 88-06. It is requested that these specific pages be substituted for those contained in our original submittal of July 6, 1987.

This change has no effect on the Safety Evaluation or the Significant Hazards Determination. This change has been reviewed by the Plant Safety Review Committee and the Nuclear Safety Review Committee. The initial processing fee of $150.00 was included with the July 6, 1987 submittal.

If you have any questions, please advise.

Very truly yours, D. A. Nauman HID/ DAN: led Attachment pc: J. G. Connelly, Jr./0. W. Dixon, Jr./T. C. Nichols, Jr.

E. C. Roberts W. A. Williams, Jr. J. C. Snelson J. N. Grace G. O. Percival J. J. Hayes, Jr. R. L. Prevatte General Managers J. B. Knotts, Jr.

C. A. Price H. G. Shealy R. B. Clary NSRC W. R. Higgins RTS (TSP 880001)

R. M. Campbell, Jr. NPCF K. E. Nodland File (813.20) l l

l _ .___ , _ _

Attachment to Document sontrol Letter -

April 28, 1988 Page 1 of 3 mp w

Id 6,0 ADMINISTRATIVE CONTROLS 6.T RfSPONSIBILITY 6.1.1 The Director Nuclear Plant Operations shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence. The title Director, Nuclear Plant Operations, is synonymous to the titles Manager, Virgil C. Summer Nuclear Station. Station Manager or Plant Manager.

6,1,2 The Shift Supervisor shall be responsible for unit operations. A t management directive to this effect, signed by the Vice President.

Nuclear Operations, shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION 6.2.1 Offsite and Onsite Oraanizations Offsite and Onsite organizations shall be established for unit operation and corporate management, respectively. The offsite and onsite organizations shall include the positions fer activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility and communication shall be ,

^

l established and defined from the highest levels through intermediate levels to and including all operating organization positions. Those relationships shall be documented and updated, and appropriate, in the form of organizational charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. The organizational charts will be documented in the FSAR and updated in accordance with 10CFR50.71(e).

b. The Director, Nuclear Plant Operations, shall be responsible for overall unit safe operation and shall have control over onsite activities necessary for safe operation and maintenance of the plant.

c. The Vice President, Operations Division, shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety. ,

d. The individuals who train the operating staff and those wns carry out the health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independent from operating pressures.

SUMMER - UNIT 1 6-1

Attachment to Document control Letter r April 28, 1988 Page 2 of 3 6.2.2 Unit Staff DRAFI

a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b. At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3 or 4, at least one Licensed Senior Reactor Operator shall be in the Control Room,

c. A health physics technician # shall be on site when fuel is in the reactor.

d. All CORE ALTERATIONS shall be observed and directly supervised by either & licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

e. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:

a. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time,

b. An individual should not be permitted to work more than i 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time,

c. A break of at least eight hours should be allowed between work periods, including shift turnover time,

d. Except during extended shutdown periods, the use of overtime should be considered on an individue.1 basis and not for the entire staff on a shift. ,

1. The health physics technician composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill required positions.

l SUMMER - UNIT 1 6-2

~

Attachment to Documeni control Letter April 28, 1988 Page 3 of 3 DRAFT Any deviation from the above guidelines shall be authorized by the Director, Nuclear Plant Operations or his deputy, or higher levels of management, in accordance with established procedures and with documentation of basis for granting the deviation. Except during extended shut own periods, controls shall be included in the procedures su that individual overtimeshallbereviewedmonthlyby\h th Director, Nuclear Plant Operations or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

SUMMER - UNIT 1 6-3

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DISTRIBUTION FOR MEETING

SUMMARY

DATED:

OsilieFriis<

~NRC"PDR ~ '

Local PDR PDII-1 Reading P.~ Anderson J. Hayes OGC-WF E. Jordan J. Partlow .

ACRS (10)

R. Prev 3tte H. Dance cc: Licensee / Applicant & Service List l

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