ML20245D014
| ML20245D014 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/19/1987 |
| From: | Emerson F CAROLINA POWER & LIGHT CO. |
| To: | Helme R CAROLINA POWER & LIGHT CO. |
| Shared Package | |
| ML20245C996 | List: |
| References | |
| FOIA-87-707 GL-87-02, GL-87-2, NUDOCS 8711040299 | |
| Download: ML20245D014 (7) | |
Text
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CP&L Carolina Power & Light Company Brunswick Steam Electric Plant many Corer. nun <fene March 19, 1987 MEMORANDUM TO:
Mr. R. E. Helme FROM F. A. Emerson SUBJECT Integrated Schedule of PRA Activities Attached. is the c'urrent '. integrated sched'ule for PRA activities at Brunswick.
All activities for Contra'ct XT60000054 have been completed, and are no longer shown on the schedhle._ Significant information on the status of Contract ZT60000070 activities, and on ONS TRA activities not directly related to this contract, is, provided below Contract ZT60000070-1.
The Unit 2 risk assessment model (not inclu' ding fire, flood, and seismic analysis results) have been incorporated -into the PRA Workstation sof tware and provided to CP&L. The corresponding Unit I risk assessment model will be provided to CP&L by March 31. Fire, flood, and seismic analysis results will be completed by April 30 and incorporated into the workstation by May 15.. These dates are two months behind. the original schedule due to extensive problems. encountered by EI. in developing a new and more useful software package. These delays have not seriously impacted ONS PRA activities.
2.
Preliminary seismic ' flooding, and fire analysis results have been provided to CP&L. These early results indicate that fire and seismic contributors dominate. core damage frequency; however, these results are being reviewed to remove unduly conservative assuantions.
3.
EI containment thermal hydraulic analysis will be complete by March 31, as scheduled. However, the downstresa containment structural analysis will not be completed until May 31. Enough information. will be available from the structural analysis to complete containment event tree quantification by May 15, and incorporation of the containment event trees in the PRA i
Workstation by May 31.
4.
Uncertainty analysis will be complete by May 31, and the overall project by June 30.
ONS Activities 1.
Modification and project reviews are ongoing.
2.
It is very uncertain as to when the three major regulatory initiatives shown on the schedule will be formally issued by the NRC. It appears that 8711040299 871102 h:
1 1,.
L
. Helme -M:rch 19, 1987 l
the risk assessment tools necessary to address each issue will be in place when needed.
3.
The applicability of our seismic analysis (currently in progress) to
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Generic Letter 87-02 (seismic adequacy of operating plant equipment) is currently being evaluated.
Problems 1.
The FRA Workstation software appears to be a useful tool for our purposes.
l.
It. appears, however, that additional enhancements are necessary to optimise its usefulness. We will discuss with EI next week the development of these enhancements.
2.
As indicated
- above, ways to address the high seismic and fire contributions to CDF are being discussed with EI.
The next status report will be provided by April 10. 1987. Please contact me if you have any questions about' these activities.
FAE:hd Encs.
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V.J.02,Jeffks ht ibuit M8h" I
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INTEGRATED SCHEDULE OF PRA ACTIVITY AS OF MARCH 19, 1917 I
I MARCH APRIL MAY l
JuuE 1
JULY t
i ACilVlilES I
1987 1
1987 1
1 1997 I
1987 1
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! LEVEL 1 MODEL ON ON WORISTAi!ON !
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PLANT-SPECIFIC DATA FOR BSEP PRA
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Initiatina Events l
Plant-specific data were used for both Units 1 and 2.
Generic frequencies f or EPRI categories (using NUREG/CR-3862) were updated (single-stage Bayesian) using BSEP data for 1981 through 1985. The BSEP scram frequency has improved sipificantly conpared with pre-1981, so 1981 through 1985 was chosen to most accurately represent the present plant behavior.
The 1981 l
through 1985 results are'typica' of industry averages. See Tables M.3.2-6, l
-7, and -8 (Section M.3.2 of the final report) for more detail.
Test and Maintenance Outages I
Plant-specific data on test and maintenance outages (1981-1985) was used for all systems mo' deled.
A " list of test and maintenance outage events is presented in Table 1.
In general, the outages are hiper than the industry average and significantly affect the PRA results.
Conponent Failure Rates Plant-specific data on conponent failure rates used in the BSEP PRA include the following:
(1) diesel generator failure-to-start (last 100 demands),
(2) HPCI turbine-driven punp failure-to-start (1982-1985),
(3)
RCIC turbine driven punp failure-to-start (1982-1985), and (4)
RHR punp failure-to-start (no failures).
Generic f ailure rates were updated (single-stage Bayesian) using the plant-specific data. The diesel generator data are good and are typical of the industry average.
The HPCI and RCIC data indicate f ailure rates significantly higher than the industry average.
RHR data indicate industry average performance.
1 TABLE l'
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' PLANT-SPECIFIC TEST AND MAINTENANCE OUTAGES l
Identifier Unit 2 Unit 1 Notes DGP-DGN-TM-DIMA 1.0E-2.
0.0057 Unit specific difference
.DGP-DGN-TM-D2MU 1.0E-2 0.0057 Unit specific difference DGP-DGN-TM-D3MA 1.0E-2' O.0057 Unit specific ' differ'ance DGP-DGN-TM-D4MA
.1.0E-2 0.0057
. Unit specific difference '
HPC-TDP-TM-HPTDP 4.3E-2 5.9E-2 Unit specific difference RCI-TDP-TM-RCPMP
.3.6E-2 5.2E-2 Unii; specific difference SWS-HTX-TM-00061
. S;0E-4 5.8E-4 Un'it specific ' difference-only in the total ugit operating hou(rs SWS-HTX-Th000G2
'.0E-4 5.8E-4 Unit specffEdifference _(onl 5
the total unit operating hours ~ y in.
SWS-HTX-TM-00DG3'
~ 5.0E-4 5.8E Unit specific difference (oaly in the total unit operating hours SWS-HTX-TM-00DG4 5.0E-4 5.8E-4 Unit specific difforence '(only in the total unit operating hours SWS-HTX-TM-ORM2A 1.3E-3 5.4E-3 Unit specific difference SWS-HTX-TM-ORM28' 1.3E-3 5.4E-3 Unit specific difference SWS-HTX-TM-0CS2A 1.0E-3 2.1E-3 Unit specific difference SWS-HTX-TM-0CS2B 1.0E-3 2.1E-3 Unit specific difference SWS-HTX-TM-LOOPA 4.6E-2 3.3E-2 Unit specific difference SWS-HTX-TM-LOOPB 4.6E-2 3.3E-2 Unit specific difference SWS-HTX-TM-RHR2C 1.2E-4 1.5E-2 Unit specific difference SWS-HTX-TM-RHR2D 1.2E-4 1.5E-2 Unit specific difference SWS-HTX-TM-RHP2A 4.6E-4 3.2E-3 Unit specific difference SWS-HTX-TM-RHP28 4.6E-4 3.2E-3 Unit specific difference SWS-M)P-TM-RHR2A 9.4E-3 2.2E-2 Unit specific difference l
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TABLE 1 (Cont'd)
Identifier
. Unit 2 Unit 1 Notes SWS-MP-TM-RNR2B 9.4E-3 2.2E-2 Unit specific difference i
SWS-EP-TM-RHR2C 9.4E-3 2.2E-2 Unit specific difference SWS-EP-TM-RHR2D 9.4E-3 2.2E-2 Unit specific difference
,.9 SWS-MP-TM-COM2C 5.0E-1 5.0E-1 Assumed SWS-E P-TM-NUC2B 5.0E-1 5.0E-1 Assumed RCM-ACX-TM-CSC2A 1.4E-5 1.6E-5 Unit specific difference (only in 1
the total unit operating hours)
RCH-ACX-TM-CSC2B l'.4E-5._ 1.6E-5 Unit specific difference. (only in the total unit operating hours).
RHR-EP-TM-C002A 1.6E-3 5.2E-4 Unit specific difference o
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RHR-MP-TM-C002B 1.6E-3 5.2E-4 Unit specific difference RHR-2P.-1N-C002C 1.6E-3 5.2 E-4 Unit specific difference RHR-E P-TM-C0020 1.6E-3 5.2E-4 Unit specific difference RHR-PTF-TM-LOOPA 1.8E-2 7.4E-3 Unit specific difference RHR-PTF-TM-LOOPB 1.8E-2 7.4E-3 Unit specific difference SLC-M P-TM-PW A 7.9E-2 1.1E-2 Unit specific difference SLC-M P-TM-PW 8 7.9E-2 1.1E-2 Unit specific difference DGH-ICC-TM-FANA 1.0E-4 1.0E-4 Generic
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DGH-ICC-TM-FAN 8 1.0E-4 1.0E-4 Generic DGH-ICC-TM-FANC 1.0E-4 1.0E-4 Generic AD S-ACT-TM-TRNA 1.0E-4 1.0E-4 Generic ADS-ACT-TM-TRN8 1.0E-4 1.0E-4 Generic C SS-M P-TM-PA 3.0E-3 6.3E-4 Unit specific difference C SS-M P-TM-PB 3.0E-3 6.3E-4 Unit specific difference RHR-PTS-TM-LOOPA 7.5E-3 6.4E-3 Unit specific difference RHR-PTS-TM-LOOPB 7.5E-3 6.4E-3 Unit specific difference
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