ML15244A672
| ML15244A672 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/24/1991 |
| From: | Wiens L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9111060279 | |
| Download: ML15244A672 (20) | |
Text
.R0 UNITED STATES 0
NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20555 October 24, 1991 Doc t*fls. 50-269,59-270, and 50-287 LICENSEE: Duke Power Company FACILITY: Oconee, Units 1, 2 and 3
SUBJECT:
SUMMARY
OF MEETING WITH DUKE POWER COMPANY CONCERNING SHUTDOWN TECHNICAL SPECIFICATIONS AT OCONEE NUCLEAR STATION On October 9 1991 the NRC staff met with representatives of Duke Power Company (DPC3 to discuss Oconee Technical Specifications (TSs), operating procedures and system designs with respect to their adequacy during shutdown operations. The NRC staff had requested the meeting as a result of concerns raised in these areas after a review of recent events at Oconee Unit 1 and an earlier event at Oconee Unit 3. Specifically, the NRC had requested DPC to review the current Oconee TS against another B&W plant's approved TS, identify any significant differences and then discuss any proposed corrective actions. If the review identified any operating procedure deficiencies or system design deficiencies, proposed corrective actions in these areas were to, be discussed also.
After opening remarks, a presentation was made covering a proposed modification to the Oconee Unit 1 and 2 Decay Heat Removal (DHR) system. The proposed modifications would allow either decay heat removal cooler to be used during the full range of system pressures for which decay heat removal is required.
Presently only the B train cooler can be used above approximately 125 psig reactor system pressure due to design limitations of portions of the system, and then only with system line-up manipulations that directs reactor coolant flow through the cooler prior to going through the DHR pump so that the pump head is not added to the pressure that the DHR cooler is exposed to. The proposed modification would replace components such that the A DHR cooler and associated piping would be rated for full DHR system pressure. The present system line-up manipulation would still be necessary in order to use the B DHR cooler at elevated pressures.
The next presentation covered the review of Oconee TS. Several areas were identified where significant differences existed between Oconee TS and the approved standard TS (Crystal River TS were used for this comparison). For each case, DPC proposed to resolve the differences by one of several methods.
In several cases, a change to the Oconee Selected Licensee Commitment (SLC)
Manual was proposed. The SLC manual is Chapter 16 of the Oconee Final Safety Analysis Report (FSAR) and contains requirements similar to those in the TS but which are not of a level of importance to warrant inclusion in the TS.
9111060279 911024 PDR ADOCK 05000269 Ia sNRC LE CuENiITER C PY
October 24, 1991 Although a part of the FSAR, it is maintained in a separate manual for ease of use by the operators. In other cases, DPC proposed to issue TS interpretations to resolve the issue, while in the area of electrical specifications, DPC indicated that an in-progress effort to revise the Oconee electrical specifica tions would address the issue. In one area DPC indicated no change was necessary.
DPC generally did not propose TS revisions because of the ongoing NRC initiative in the area of shut-down technical specifications.
After a brief caucus, the NRC staff stated that the approach being proposed by DPC was acceptable in addressing the differences in the Oconee TS. DPC was requested to formally document their commitment to implement the SLC manual changes and TS interpretations, including the implementation schedule, and to commit to include the operating philosophy reflected by these changes in the planning for the next Oconee Unit 3 outage if the actual changes were not yet in place. DPC agreed to the NRC requests and intends to make a formal submittal on these issues on or about October 23, 1991. With regard to the proposed modification to the DHR system, some concern was expressed with the need to manipulate the system line-up in order to use the B DHR cooler even after the modification, with the resultant increased vulnerability to operator error. The NRC staff requested a follow-on meeting with DPC to discuss this modification in more detail. A schedule for this meeting was to be determined later.
Meeting attendees are listed in Enclosure 1. The agenda for the meeting is provided as Enclosure 2. Copies of the slides and handouts used during the various presentations are provided as Enclosure 3.
Leonard A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/I Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/enclosures:
See next page
0 0
2 -
October 24, 1991 Although a part of the FSAR, it is maintained in a separate manual for ease of use by the operators. In other cases, DPC proposed to issue TS interpretations to resolve the issue, while-in the area of electrical specifications, DPC indicated that an in progress effort to revise the Oconee electrical specifications would address the issue. In one area DPC indicated no change was necessary.
DPC generally did not propose TS revisions because of the ongoing NRC initiative in the area of shut-down technical specifications.
After a brief caucus, the NRC staff stated that the approach being proposed by DPC was acceptable in addressing the differences in the Oconee TS. DPC was requested to formally document their commitment to implement the SLC manual changes and TS interpretations, including the implementation schedule, and to commit to include the operating philosophy reflected by these changes in the planning for the next Oconee Unit 3 outage if the actual changes were not yet in place. DPC agreed to the NRC requests and intends to make a formal submittal on these issues on or about October 23, 1991.
With regard to the proposed modification to the DHR system, some concern was expressed with the need to manipulate the system line-up in order to use the B DHR cooler even after the modification, with the resultant increased vulnerability to operator error. The NRC staff requested a follow-on meeting with DPC to discuss this modification in more detail. A schedule for this meeting was to be determined later.
Meeting attendees are listed in Enclosure 1. The agenda for the meeting is provided as Enclosure 2. Copies of the slides and handouts used during the various presentations are provided.as Enclosure 3.
/s/
Leonard A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/enclosures:
See next page DISTRIBUTION:
GHolahan, 8E2 GBelisle, Ru Docket File AChaffee, 1A1 Jdohnson, Rh NRC & Local PDRs MBiamonte, 10D24 MMarkley, 1OH11 PDII-3 R/F JBall, 9A1 dShackelford, R1 Oconee R/F CRossi, 11D4 MCaruso, 8E23 FMiraglia, 12G18 BLeFave, 801 SAthavale, 9A1 JPartlow, 12G18 JKnight, 7E4 WLyon, 8E23 SVarga SDiab, 10E4 PHarmon, Rh GLainas TChandrasekaran, 8D1 REmch, lIE22 EMcKenna LWiens PHearn, 11E22 ACRS (10), P-315 OWechselberger, 17G21 L *PD -3 PM:PIII-33 LBLWiens:cw EMcKj~n DOCUMENT NAME: SUM OF MTG W/DPC 10/9
Oconee Nuclear Station Duke Power Company cc:
Mr. A. V. Carr, Esq.
Mr. Stephen Benesole Duke Power Company Duke Power Company 422 South Church Street Post Office Box 1007 Charlotte, North Carolina 28242-0001 Charlotte, North Carolina 28201-1007 J. Michael McGarry, III, Esq.
Winston and Strawn Mr. Alan R. Herdt, Chief 1400 L Street, NW.
Project Branch #3 Washington, DC 20005 U. S. Nuclear Regulatory Commission 101 Marietta Street, NW., Suite 2900 Mr. Robert B. Borsum Atlanta, Georgia 30323 Babcock & Wilcox Nuclear Power Division Ms. Karen E. Long Suite 525 Assistant Attorney General 1700 Rockville Pike N. C. Department of Justice Rockville, Maryland 20852 P.O. Box 629 Raleigh, North Carolina 27602 Manager, LIS NUS Corporation Mr. R. L. Gill, Jr.
2650 McCormick Drive, 3 Floor Nuclear Production Department Clearwater, Florida 34619-1035 Duke Power Company P. 0. Box 1007 Senior Resident Inspector Charlotte, North Carolina 28201-1007 U. S. Nuclear Regulatory Commission Route 2, Box 610 Mr. M. S. Tuckman Seneca, South Carolina 29678 Vice President Nuclear Operations Regional Administrator, Region II Duke Power Company U. S. Nuclear Regulatory Commission P. 0. Box 1007 101 Marietta Street, NW., Suite 2900 Charlotte, North Carolina 28201-1007 Atlanta, Georgia 30323 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 County Supervisor of Oconee County Walhalla, South Carolina 29621
ENCLOSURE 1 DUKE/NRC MEETING ON ONS TS ATTENDEES NAME ORGANIZATION Len Wiens NRR/PDIH-3 David Matthews NRR/PDII-3 S. Varga NRR/DRPE Gary M. Holahan NRR/DST Thomas Curtiss Duke Power/Oconee M. S. Tuckman Duke Power H. B. Barron Duke Power A. E. Chaffee NRR/EAB G. C. Lainas NRR/ADRII MaryAnn Biamonte NRR/DLPQ J. R. Ball NRR/RSIB C. E. Rossi NRR/DOEA Bill LeFave NRR/DST Jim Knight NRR/DST/SELB Sammy Diab NRR/RAB T. Chandrasekaran NRR/DST/SPLB Rich Emch NRR/OTSB Pete Hearn NRR/OTSB G. A. Belisle NRC RH Section Chief J. Johnson NRC/RII DRP M. Markley NRR/LPEB Jeff Schackelford NRC/RII/ORS Mark Caruso NRC/SRXB S. V. Athavale NRC/SICB D. C. Fischer NRC/NRR/DOEA/OEAB Warren Lyon NRR/SRXB Paul Harmon RII -
Resident Insp.
Tony Pietrangelo NUMARC Philip J. North Duke Power Co.
Jim Eaton NUMARC Mike Schoppman Florida Power & Light Co.
David Deatherage Duke Power Co.
Stephen Benesole DPC Ken Wilson FPC/BWOG
0 ENCLOSURE 2 DUKE POWER - NRC MEETING OCONEE SHUTDOWN TECHNICAL SPECIFICATIONS October 9, 1991
- 1.
OPENING REMARKS Mike Tuckman II.
SD REQUIREMENTS IMPLEMENTATION Brew Barron III.
SD TECH SPECS COMPARISON Tom Curtis IV.
DISCUSSION (All)
SHORT TERM MEASURES SELECTED LICENSEE COMMITMENTS (SLC)
TECH SPEC INTERPRETATIONS TECH SPEC / LICENSE AMENDMENTS
TECH SPEC COMPARISON OCONEE VS. CRYSTAL RIVER & CATAWBA MODES 5&6 FOCUS ON SHUTDOWN HARDWARE DESIGN ADEQUACY ASSESSED
MODE DEFINITIONS B&W Standard TS Mode keff Temp Cold Shutdown 5
<.99
<200 Refueling 6*
<.95
<140 Shutdown RV Head unbolted or removed and fuel in vessel B&W Custom TS Mode keff Temp Cold Shutdown N/A SDM>1
<200 Refueling N/A SDM>1
<140 Shutdown w
No statement regarding RV head status.
Revised Standard TS Mode keff Temp Cold Shutdown 5
<.99
<200 Refueling 6*
<.95 ref N/A Shutdown to LCO
LCO APPLICABILITY STANDARD TS:
APPLICABLE MODES LISTED OCONEE:
APPLICABLE CONDITIONS STATED IN LCO OR ACTION STATEMENT END POINT
Comparison of STS with ONS TS Mode Definitions Modes Description ONS Short Provisions Term Solution 6
Definition of Present Interpret RV Head procedures TS as STS Status and TS's (Unbolted vs apply to Bolted) ref ueling operations FROM 7043738033 10-08-91 03:14 PM PO
Comparison of STS with ONS TS Reactivity Control Modes Description ONS Short Provisions Term Solution 5 & 6 One boron Procedures Develop injection require HPI SLC like flowpath pump @
STS (CBAT or
> 100 psig BWST)
Procedures require 1 LPI pump for refueling
g S
Comparison of STS with ONS TS Coolant Circulation Modes Description ONS Short Provisions Term Solution 5
One RCS Procedures Develop loop w/
require SLC like RCP/SG and single loop STS DHRor2 DHR loops GL88-17 SLC requires two DHR pumps 6
1 LPI pump in Procedures same (FTC operation require one full) cooling train for refueling operations 6
1 LPI pump in Procedures same (FTC operation and require one not other train DHR train full) operable
Comparison of STS with ONS TS Instrumentation Modes Description ONS Short Provisions Term Solution CRD's Manual &
normal Develop energ-automatic Rx config.
SLC ized trip CRD's SR and IR TS 3.5.1:
same energ-flux detectors 1 SR & IR ized for startup 2 SR flux TS 3.8:
same detectors 2 SR for RF Procedures require SR when fueled 5 with 1 RPI for normal same CRD's each rod not config.
energ-fully inserted ized
Comparison of STS with ONS TS Electrical Modes Description ONS Short Provisions Term Solution 5,6 AC Sources Procedures Submit TS AC Distrib.
to address DC Distrib.
SLC for electrical DC Sources GL88-17 reqmnts at Applies at shutdown low RCS inventory Meeting requested with NRR later this month to discuss TS submittal.
Comparison of STS with ONS TS Refueling Operations Modes Description ONS Short Provisions Term Solution During Cont.
TS 3.8.7 Revise TS core penetrations Procedure interpret, altera-req'd closed tions or auto close During Refueling Procedures No change core bridge hoist altera-capacity and tions overload cutoff During FTC full Procedures Develop core SLC altera tions FROM 7043738033 10-08-91 03:14 PM Pi1
SUMMARY
STS SD REQUIREMENTS GENERALLY MET BY PROCEDURES SIGNIFICANT UPGRADES IN REQUIREMENTS FOR REDUNDANT DHR AND BORATION PATHS SHORT TERM REGULATORY COMMITMENTS WILL FILL SHUTDOWN TECH SPEC "HOLES" DESIGN ADEQUACY VERIFIED THROUGH ABILITY TO MEET SHUTDOWN STS LONG TERM PLAN INCLUDES SHUTDOWN TS UPGRADES AND POTENTIAL MOD FROM 7043738033 10-08-91 03:14 PM Pl2
RCSS LP-LP-7 LP[U-3 LP PIPP 6 LP5 E
DECA LPC.ONEEA LOLRE S F NUEPI SYSTEIII OOER
P-1
RCSRCS LP I LP-?
LPIRJPP LLP 1
LPI PUMP -ABA OCO11LP-1 LOW PESSUE I NECT ONLSST12 SPIC74E ELIGNI ENT
Meeting Summary, Memoranda for Trip Reports or Site Visits Docket File NRC PDR Local PDR F. Miraglia 12-G-18 J. Partlow 12-G-18 S. Varga 14-E-4 G. Lainas 14-H-3 F. Hebdon M. Sanders T. Ross J. Williams D. Moran B. Wilson RI J. Weschelberger 17-G-21 P. Kellogg RHI C. Patterson RH T. Peebles RI
- 8. Bearden RI 0GC 15-B-18 E. Jordan MNBB-3701 ACRS (10)