ML20214Q176

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Summary of 870518 Meeting W/Util Re NRC Reorganization Concerning Philosophy & Implementation.Status of Current & Future Licensing Items Also Reviewed.Lists of Attendees & Status of Licensing Items Encl
ML20214Q176
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 05/29/1987
From: Hopkins J
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8706040268
Download: ML20214Q176 (10)


Text

r- y Docket No. 50-395 LICENSEE: South Carolina Electric and Gas Company FACILITY: V. C. Summer Nuclear Station

SUBJECT:

SUP94ARY OF MEETING WITH SOUTH CAROLINA ELECTRIC AND GAS COMPANY GENERAL On May 18, 1987, the NRC staff met with the South Carolina Electric and Gas Company (SCE&G) to discuss the NRC reorganization and the status of licensing actions for the V. C. Summer Nuclear Station. The meeting was held in Bethesda, MD. A list of those persons who attended the meeting is included as Enclosure 1.

DISCUSSION The NRC reorganization was discussed with regard to philosophy and implementation. Also, the status of current and future licensing items was reviewed. Those licensing items are listed in Enclosure 2.

/s Jon B. Hopkins, Project Manager Project Directorate 11-1 Division of Reactor Projects - I/II

Enclosures:

As Stated cc: See Next Page DISTRIBUTION:

E Docket: File; ,

NRC PDR PDII-1 r/f JHopkins EAaensam 0(aC-B EJordan JPartlow NRC Participants ACRS(10)

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LA:PDII-I D:PDII-I O

/JHopkins/dsf r PAnderson EAdensam 05/g/87 05/jj/87 05/t.;/87 8706040268 DR 870529 ADOCK 05000395 PDR

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

Mr. William A. Williams, Jr.

Technical Assistant - Nuclear Operations Santee Cooper P.O. Box 764 (Mail Code 167)

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

Bishop, Liberman, Cook, Purcell and Reynolds 1200 17th Street, N.W.

Washington, D. C. 20036 Resident Inspector /Sumer NPS c/o U.S. Nuclear Regulatory Comission Route 1, Box 64 Jenkinsville, South Carolina 29065 Regional Administrator, Region II U.S. Nuclear Regulatory Comission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Chairman, Fairfield County Council P.O. Box 293 j Winnsboro, South Carolina 29180 Attorney General

Pox 11549 Columbia, South Carolina 29211 Mr. Heyward G. Shealy, Chief i Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 l

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ENCLOSURE 1 MEETING WITH SCE&G MAY 18, 1987 NRC SCE&G J. Hopkins J. Connelly E. Adensam A. Paglia G. Lainas M. Williams S. Varga i

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M:y 15,1987 LICENSING ITEMS STATUS LlsT V. C. SUMME R NUCLE AR STATION TECHNICAL SPECIFICATION REVISIONS SUBMITTE D TO NRR FEDERAL NRR TITLE SUBMITTAL REGISTER NRR APPROVAL SCE 8G

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REVISION / PROBLEM DATE(S) 155UANCE TECHNICAL DATE REQUIRED NRR TAC. NO STATUS (Estimated REVIEW (Estimated DATE Date) Date) 3/4 8 " AC Sources" Revises the Technical Speofication to combine 06-10-85 07-17-85 Remainmg TS Partial TS (AMM) testing to reduce thermaltransients change 12-06-85 Exp 08-16-85 Request request 59451 18 months surveillante to ref ueling, change under review approved loading limits to loading bands, and other 06-04-86 07-30-86 05-30-86 clarifying changes E x p. 07-04-86 (RAl to be sent) (2nd Quarter) 3616 " Containment Tech Spec revised to(hange the 09-16-86 11-05-86 (05-31 87)

(RJB) Structural number / sample of tendons to be tested. E x p.12-05-86 Integrity" deleted specific tables, and revised the minimum required average tendon force for each group.

33-2 " Reactor Trip Technwal Speofication to be revised to 12-08-83 05-06-87 (06-01-87)

< Tbl 4 31 System opt.mae reactor tr p breaker testing (HID) Surveillance a Requirements" i

"ESF/SW System Resolve discrepanoes between SW system and 12-12-86 01-14-87 Cheng Li (06-30-87)

3 3.2 Tbl. 3 3 5 Discrepancies" RBCU Tech Spec. ESF Response time Exp 02-13-87 (MDB) requirements and actual operational m

capabilities. 2 o

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M:.y 15,1987 ,

LICENSING ITEMS STATUS LIST V, C. SUMME R NUCLE AR STATION j TECHNICAL SPECIFICATION REVISIONS SUBMITTE D TO NRR FEDERAL NRR TITLE SUBMITTAL REGISTER NRR APPROVAL SCE &G

'{ REVISION / PROBLEM DATE(S) ISSUANCE TECHNICAL DATE REQUIRED NRR TAC. NO. STATUS (Estimated REVIEW (Estimated DATE

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Date) Date) 4 6 2 3 a.2 " Reactor Bldg. Revise Tech. Spec. to require less than 2000 01-20-87 02-26-87 SER On Hold 4th refueling (HID) Cooling Sys? gpm to RBCU's. 02-24-87 Exp 03-28-87 Approved (Giardina) i 3 3.3 7

  • Fire Detection Evaluate removmg all Fire Protection from 03-31-87 (07-01-87) l System" Tech. Spec. and address m separate document j 3791 " Fire Suppression (FSAR)

System

  • 3792 " Spray and/or Sprinkler Systems
  • 3.793 "CO2 System" 3794 " Fare Hose Staton*

3795 " Yard Fire Hydrants and Hose Stations

  • 3.7.10 " Fire Rated (HID) Assemblies" 4

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Mcy 15,1987 ' ' ,

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LICENSING ITEMS STATUS LIST V. C. SUMME R NUCLE AR $TATION TECHNICAL SPECIFICATION REVISIONS SUBMITTED TO NRR a i FEDERAL NRR TITLE SUBMITTAL REGISTER NRR APPROVAL SCE&G REVISION / PROBLEM DATE(S) ISSUANCE TECHNICAL DATE REQUIRED NRR TAC. NO. STATUS (Estimated REVIEW (Estimated DATE

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j Date) Date)

, 3/4 12 " Radiological Allows program changes to be w.stiated based 03-26-87 (07-01-87) i (DCB) Environmental on operational experience. Reduces number

! Monitoring" of continuous air sampling location, adds l finished water control sample location, reduces number of broadleaf vegetation sample locations.

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i Shent4Cf 8 May 15,1987l l' .

l LICENSING ITEMS STATUS LIST f V.C. SUMMER NUCLEAR STATION

' TECHNICAL SPECIFICATION REVISIONS TO BE SUBMITTED 2ND QUARTE R 1987 FEDERAL NRR TECHNICAL TITLE SU8MITTAL REGISTE R NRR APPROVAL SCE8G SPECIFICATION REVISION / PROBLEM DATE(S) ISSUANCE TECHNICAL DATE REQUIRED

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! (ISSUE MANAGER) NRR TAC NO. STATUS (Estimated REVIEW (Estimated DATE Date) Date) 3/4 1.12 Challed Water Determine feasibility of addmg the Chilled (WRH) System Water System to the Tech. Spec.

3/43.2 ESFAS Revise Table 3 3 5 to change notes related to Instrumentation SI response times (2) 331 "RPS Need to revise Spec. to implement To be split (AMM) Instrumentation" Westinghouse Owners Group optimization into two program submittals 3/4 4 5 " Steam Revise recent Technical Specification change (TRW) Generator" to correct paragraph numbers.

(Administrative Change) 4311 " Reactor Trip Apply note 10 to items 15 and 16 in order that (MGC) System

  • setpoint verification will not be required.

Figures 6 2 & 6 4 Organizational Revise Tech. Spec. to delete organizational (HID) and Training charts and revise training requirements.

(RJ8) Changes I

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LICENSING ITEMS STATUS LIST V. C. SUMMER NUCLE AR STATION TECHNICAL SPECIFICATION REVISIONS TO BE SUBMITTED 3RD QUARTER 1987 FEDERAL NRR TECHNICAL TITLE SUBMITTAL REGISTER NRR APPROVAL SCE&G SPECIFICATION REVI510N/ PROBLEM DATE(5) ISSUANCE TECHNICAL DATE REQUIRED (ISSUE MANAGER) NRR TAC NO. STATUS (Estimated REVIEW (Estimated DATE Date) Date) 381.1 *A.C Sources

  • Evaluate addressing ioad Sequencer in a (WRH) separate specification (Need NRR answer to previous submittal for 3/4 8) 3716 *Feedwater Revise Tech Spec Bases.

(DBM) Isolation Valves" (3) 34S' ' Steam 4 4 5 3 C 3 requires additional unscheduled lSt Engr /Maint.

(MDB) Generator

  • if there is a LOCA requirmg ESF action. This to evaluate needs to be clarified to better describe when submittal an ISI is needed subsequent to this event. based on W_

Scope Document.

Tbl 3.3-2 Reactor Trip include Response Time and revise bases (CJM) System Inst. (OPAT)

Response Times 3462* "RCS Operational Evaluate relaxing RCS Pressure Isolation Valve Perform (AMM) Leakage

  • leakage requirement and/or evaluate deletion feasibility (WRH) of some valves from Table 3 4-1. study. (Need W input )

3842 MOV Thermal Delete surveillance requirements for thermal (WRH) Overload overloads that are continously bypassed. Add Protection and valves to hst and correct typos.

Bypass Devices

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I LICENSING ITEMS STATUS LIST V. C.SUMME R NUCLE AR STATION TECHN! CAL SPECIFICATION REVISIONS TO BE SUBMITTED 4TH QUARTER 1987 FEDERAL NRR TECHNICAL TITLE SUBMITTAL REGISTER NRR APPROVAL SCE8G SPECIFICATION REVISION / PROBLEM DATE(5) ISSUANCE TECHNICAL DATE REQUIRED (ISSUE MANAGER) NRR TAC NO. STATUS (Estimated REVIEW (Estimated DATE Date) Date)

(3) 3712

  • Emergency LCO requirements is for operable pumps and Perform (DBM) Feedwater flow paths; however Action Statement only feaubility (WRH) System
  • addresses pump (s) being inoperable. Need to study. (Need modify Action Statement to address G/C input )

enoperable flow paths (M 3 3.2 *ESF Need to revise Spec.toimplement Will need (AMM) instrumentation

  • Westinghouse Owners Group optimization NRCinput on programs. 3.3.t review prior to submittat i

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L LICENSING ITEMS STATUS LIST V. C. SUMMER NUCLEAR STATION OTHER TECHNICAL REVIEWS l

FEDERAL NRR

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ITE M DESCRIPTION ESTIMATED ACTUAL REGISTER NRR APPROVAL SCE8G i.iSUE SU8MITTAL SU8MITTAL ISSUANCE TECHNICAL DATE REQUIRED l

1 MANAGER) NRR TAC. NO. DATE DATE(S) (Estimated REVIEW (Estimated DATE Date) Date) f 40 Year O L. Extends O L to 40 years from date of issuance 2nd Qtr '87 0842-85 0547-86 (AMM) E mp. 06-06-86 59402 (7) Control CRDR Final Report to be submitted addressing 2nd Qtr. *87 I Room questions received from NRC (06-21-85 )

Design Review 56167 (AMM)

(9) 0737, item Response to NRC Staf f questions (letter dated 2nd Qtr. ~87 11 D 1 7-1-85) pertaining to relief and safety valves.

I (AMM) These questions are in conjunction with I

NUREG 0737, item Il D 1.

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