ML18011A164
| ML18011A164 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/13/1993 |
| From: | Le N Office of Nuclear Reactor Regulation |
| To: | Bajwa S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9309160086 | |
| Download: ML18011A164 (10) | |
Text
SepteIher 13, 1
3 Docket No. 50-400
~DIE IBIITION See attached page MEMORANDUM FOR:
FROM:
SUBJECT:
DATE & TIME:
LOCATION:
PURPOSE:
S. Singh Bajwa, Acting Director Project Directorate II-1 Division of Reactor Projects - I/II Ngoc B. Le, Project Manager Project Directorate II-1 Division of Reactor Projects - I/II MEETING WITH CAROLINA POWER
& LIGHT COMPANY REGARDING THE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1
- Tuesday, September 21, 1993 9:30 am 12:00 pm One White Flint North 11555 Rockville Pike Room 13-B-13 Rockville, Maryland To discuss the status of licensing actions PARTICIPANTS*:
NRC N.
Le L. Phillips S.
Bajwa cc:
See next page CP&L R. Prunty et al.
Original signed by:
Ngoc B. Le, Project Manager Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
- Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy," 43 Federal
~Re ister 28088, June 28, 1978.
OFFICE NANE LA:P 1
RPE PAnd rson PM: PD21: DRPE D: PD21: DRPE NLe:dt 4 SBajwa DATE I3 93
<3 93 I5 93 Document Name:
HAR.MTG 9S09>S00az.'Va09~3 PDR
.ADOCK 05000400' PDR
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Q./de
Shearon Harris Nuclear Power Plant, Unit 1
CC:
Mr. H.
Ray Starling Manager Legal Department Carolina Power
& Light Company Post Office Box 1551
- Raleigh, North Carolina 27602 Resident Inspector/Harris NPS c/o U.S. Nuclear Regulatory Commission Route 1,
Box 315B New Hill, North Carolina 27562 Karen E.
Long Assistant Attorney General State of North Carolina Post Office Box 629
- Raleigh, North Carolina 27602 Public Service Commission State of South Carolina Post Office Drawer 11649
- Columbia, South Carolina 29211 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St.,
N.W. Suite 2900 Atlanta, Georgia 30323 Mr.
W.
R. Robinson Plant Manager Carolina Power
& Light Company Shearon Harris Nuclear Power Plant Post Office Box 165, MC: Zone 1
New Hill, North Carolina 27562-0165 Mr. Dayne H. Brown, Director Division of Radiation Protection N.C. Department of Environmental Commerce
& Natural Resources Post Office Box 27687
- Raleigh, North Carolina 27611-7687 Mr. H.
W. Habermeyer, Jr.
Vice President Nuclear Services Department Carolina Power
& Light Company Post Office Box 1551
- Raleigh, North Carolina 27602 Mr.
W. S. Orser, Executive Vice President Nuclear Gneration Carolina Power
& Light Company Post Office Box 1551
- Raleigh, North Carolina 27602
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DISTRIBUTION Routine Meetin Notice aDo"cket F-i:l'e, NRC
& Local PDRs PD ¹21 Reading T. Hurley/F. Hiraglia J. Partlow S.
Varga G. Lainas S.
Bajwa N.
Le L. Phillips P. Anderson A. Chaffee, OEAB OGC E. Jordan E. Rossi Receptionist (White Flint)
ACRS (10)
- PMAS, P. O'Dell, PHAS G. Zech, RPEB L. Plisco, EDO E. Merschoff, cc:
Licensee 5 Service List 12-G-18 12-G-18 8/E-23 11/A-1 HNBB 3701 9/A-2 12/G/18 12-E-4 10-A-19 17-G-21 Region II
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 September 9,
1993 Docket No. 50-400 MEMORANDUM FOR:
Singh S.
Bajwa, Acting Director Project Directorate II-1 Division of Reactor Projects - I/II FROM'UBJECT:
Ngoc B. Le, Project Manager Project Directorate II-1 Division of Reactor Projects - I/II
SUMMARY
OF SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1, INDIVIDUAL'PLANT EXAMINATION (TAC NO/74418)
Carolina Power 5 Light Company (CPKL) submitted its Individual Plant Examination
( IPE) report for the Shearon Harris Nuclear Power Plant, Unit 1
(Harris),
on August 20,
- 1993, in accordance with Generic Letter (GL) 88-20, "Individual Plant Examination for Severe Accident Vulnerabilities."
The Harris IPE was performed using a plant specific comprehensive probabilistic risk assessment (PRA) consistent with the method listed in section 4 of GL 88-20 and NUREG-1335,
" Individual Plant Examination:
Submittal Guidance."
The report indicates that the estimated core damage frequency from internal
- events, including flooding, is 7.0 E-5 per year, and that the licensee considers this result not atypical when compared to the PRA results of other Westinghouse pressurized water reactors.
Earlier in their study, the licensee identified a dominating contributor (approximately 50X of the total estimated core damage frequency) that consisted of sequences that involved failure of the non-vital 125 V DC electrical system.
This system provides control power to all breakers that must change position to allow the transferring of plant power from the main generator to the switchyard on a plant trip.
Consequently, a failure of the DC power system would inhibit the transferring of plant power, causing a loss of offsite power and a reliance on the emergency diesel generators:
Because of the significance of this failure mode to the IPE results, the licensee implemented procedure changes to direct local operation of the breakers in question if the DC control power failed.
The estimated core damage frequency of 7.0 E-5 per year reflects this action.
The IPE report shows that the current Harris core damage profile is not dominated by any particular accident
- sequence, and no single type of initiating event is responsible for a large part of the overall core damage frequency.
The licensee identified that, as indicated on the enclosed Figure l-l, small (3-5 inch)
LOCAs and loss of offsite power are the top two initiating event contributors accounting for about 60X of the overall core damage frequency.
Figure l-l also shows the four most frequent individual event tree sequences that account for about 70 percent of the overall core damage frequency.
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The licensee concludes that (1) based on their IPE results, there is no particular plant feature at the Harris plant that would create a unique accident type that is predominant, and (2) in accordance with GL 88-20, two unresolved safety issues (USI),
USI A-45, "Shutdown Decay Heat Removal Requirements",
and USI A-17, "Systems Interaction in Nuclear Power Plants" have both been resolved by the Harris IPE process.
Resolution of these two USIs is discussed in the report.
Original signed by:
Ngoc B. Le, Project Manager Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
Figure 1-1 DISTRIBUTION Docket File PD21 Readin TMurley FMiraglia JPartlow SVarga GLanas SBajwa NLe PAnderson RHernan WRussell AThadani
- JFlack, RES CRossi JWiggins FCongel WBeckner DWheeler g File 12-G-18 12-G-18 12-G-18 14-C-7 12-G-18 8-E-2 NLS 318 9-A-2 7-D-26 10-E-4 12-G-18 OFF1CE LA:P E
PM: PD21: DRPE D: PD21: DRPE PAnde son NAME DAZE
/
/93 Document Name:
HARIPE.MEM NLe:dt
/
/93 SBajwa
/9 /93
IPE Submittal Figure 1-1 Initiating Events and Functional Sequences Contributions to Core Damage Frequency CDF Contributions by Initiator 4%
5%
-'w9 13%
3%
3%
3%
4%
26%
34%
0 Small LOCA(3"-5") 34%
5 Loss of Offsite Power 26%
~ Other 13'Yo Q internal Flooding 5%
G Medium LOCA 5'Yo 0 Large LOCA4%
~ Loss of 6.9 kv Bus 1B-SB 4%
~ Turbine Trip 3'/o 5 Partial Loss of Feedwater 3'Yo iISGTR 3%
10%
7%
11%
CDF Contributions by Sequence 3%
3'Yo 6%
17'/o 26'/o 17%
0 Station Blackout 26%
~ Small LOCA-InJection Failure 17'Yo 8 Small LOCA-Recirculadon Failure 17%
Cl Transient w/Loss of DHR 11%
G Other 10%
0 Internal Flooding 7'Yo
~ ATWSatBOL6%
~ Medium LOCA-Reccirculabon Failure 3%
8 Large LOCA-Recirculation Failure 3%
1-9
The licensee concludes that (1) based on their IPE results, there is no particular plant feature at the Harris plant that would create a unique accident type that is predominant, and (2) in a'ccordance with GL 88-20, two unresolved safety issues (USI), USI A-45, "Shutdown Decay Heat Removal Requirements",
and USI A-17, "Systems Interaction in Nuclear Power Plants" have both been resolved by the Harris IPE process.
Resolution of these two USIs is discussed in the report.
OIiginal signed by:
Ngoc B. Le, Project Manager Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
Figure 1-1 DISTRIBUTION oDo,cue.Fi.l.e PD21 Reading TMurley FMiraglia JPartlow SVarga GLanas SBajwa NLe PAnderson RHernan WRussell AThadani
- JFlack, RES CRossi JWiggins FCongel WBeckner DWheeler File 12-G-18 12-G-18 12-G-18 14-C-7 12-G-18 8-E-2 NLS 318 9-A-2 7-0-26 10-E-4 12-G-18 LA:P E
OFFICE PAnde son IIANE
/
/93 DATE Document Name:
HARIPE.MEM PM: PD21: DRPE NLe:dt 93 0:PD21:DRPE SBajwa
/g /93