ML20106A172
| ML20106A172 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/18/1992 |
| From: | Beck G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, NUDOCS 9209250157 | |
| Download: ML20106A172 (17) | |
Text
_ _ - _ - _ _ _ _ _
PIIILADELPIIIA ELECTRIC COMPANY 10 CFR 50.54(f) j GL 87-02 Supp. 1 NUCLEAR GROUP HEADQUARTERS 95545 CHESTERBROOK BLVD.
S p em r 18, 1H2 WAYNE, PA 19087 5691 (215) M0400 Docket Nos. 50-277 50-278 NUCLEAR SERVICES DI;PARTMENT License Nos. DPR-44 DPR-56 U.
S.
Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
Peach Bottom Atomic Power Station, Units 2 and 3 Response to Generic Letter 87-02, Supplement 1,
" Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operatina Reactors, Unresolved Safety Issue (USI) A-46."
Dear Sir:
INTRODUCTION On February 19, 1987, the NRC issued Generic Letter (GL) 87-02, " Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety Issue (USI) A-46."
GL 87-0.
encouraged licensees to participate in a generic program to resolve the seismic verification issues associated with USI A-46.
As a result, the Seismic Qualification Utility Group (SQUG) developed the " Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment."
By letter dated May 22, 1992, the NRC issued GL 87-02, Supplement 1, which constituted the NRC Staff's review of the GIP and which included Supplemental Safety Evaluation Report Number 2 (SSER-2) on the GIP, Revision 2 corrected on February 14, 1992.
The letter to SQUG enclosing SSER-2 requests that SQUG member utilities provide to the NRC, within 120 days, a schedule for implementing the GIP.
By letter dated August 21, 1992, to James G.
Partlow, NRR-NRC, SQUG clarified that the 12: days would expire on September 21, 1992.
Accordingly, this lette responds to that request.
/3I l
9209250157 920918 sh PDR ADOCK 05000277
\\
l P
U. E S. Nucloer Rcquiatory Commission.
September 18, 1992 PBAPS Units 2 and 3 Page-2
~
Response to GL 87-02 Supp.'l COMMITMENT TO GIP As a member of SQUG, Philadelphia Electric Company-(PECo) commits to use the SQUG methodology as documented in the GIP, where " GIP" refers to GIP Revision 2, corrected February 14, 1992, to resolve USI A-46 at Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3.
The GIP, as evaluated by the NRC Staff, permits licensees to deviate from the SQUG commitments embodied in the Commitment sections, provided the Staff-is notified of substantial deviations prior to implementation.
PECo recognizes that the Staff's position in SSER-2 is that if licensees _use other methods that deviate from the criteria and procedures as described in SQUG commitments and in the implementation guidance of the GIP, Rev.
2, without prior NRC Staff approval, the method may not be acceptable to the Staff and, therefore, may result in a deviation from the provisions of GL 87-02.-
Specifically, PECo hereby commits to the SQUG commitments set forth in the GIP in their entirety, includjng the clarifications, interpretations, and exceptions identified in SSER-2 as clarified by the August 21, 1992, SQUG 1etter responding to SSER-2.
PECo generally will be guided by the remaining (non-commitment) sections of the GIP, i.e.,
GIP implementation guidance, which comprises suggested methods-for implementing the applicable commitments.
PECo will notify the NRC as soon as practicablo, but no later than the final USI A-46 summary report, of significant or programmatic deviations from the guidance portions of the GIP, if any.
Justifications for such deviations, as well as for other minor deviations, will be retained on site for NRC review.
IN-STRUCTURE RESPONSE SPECTRA For defining seismic demand, PECo will use the options provided in the GIP for conservative and median-centered, design in-atructure response spectra, as appropriate, depending on the building, the location of equipment in the building and equipment characteristics.
The licensing-basis safe-shutdown earthquake (SSE) in-structure response spectra may be used as one of the options-provided in the GIP for resolution of USI A-46.
The licensing-basis' spectra as described in the Updated Final Safety Analysis i
Report (UFSAR) for PBAPS Units 2 and 3 may be used and are considered to be conservative design.
The procedures and criteria which were used to generate-the licensing-basis in-structure response spectra are described in Attachment 1.
Those pages that are copies of the PBAPS UFSAR are being l
provided to the NRC for convenience.
_r U.LS.. iluclear R:gulatory Commiccion-S:ptemb;r_18, 1992 PBAPS ?Jnits-2 and 3 Pag 1 3:
R:cponce'to GL 87-02 Supp. 1 C
Realistic, median-centered in-structure response spectra may be used'as one of_the options provided in:the GIP for resolution of USI A-46.
SCHEDULE Given the magnitude of the effort required to' achieve resolution of USI A-46, final implementation must be carefully integrated with outage schedules and the seismic-" Individual Plant. Examination of External Events (IPEEE) for Severe Accident.
Vulnerabilities" response, the completion of which may be affected by the A-46 implementation start date.
Because of integration with IPEEE, and the workload set forth by the criteria of the GIP, a Seismic Evaluation Report summarizing the results of the A-46 program at PBAPS will be submitted to the NRC by November 20, 1995.
-Regarding in-structure-response spectra, if the NRC Staff
-does not respond by accepting, questioning, or rejecting the spectra within sixty (60) days from the date of this letter, the Staff is deemed to have accepted PECo's spectra, and we will proceed with implementation.
If a rejection or question is received from the Staff, we will provide additional information to. resolve the problem.
Again, if the Staff. takes no action on
-this new information for sixty (60) days from the date.of our response,-the Staff is deemed to have accepted our resolution and we will proceed with implementation.
The completion date of November 20, 1995, is based on the assumption that the implementation program will proceed on November 20, 1992.
If you have any questions, or require additional ~information regarding this submittal, please contact us.
Sincerely, G.
J. Beck Manager Licensing Section Attachment
Enclosure:
Affirmation cc: T.
T. Martin, Administrator, Region I, USNRC J.
J. Lyash, USNRC Senior Resident Inspector, PBAPS b
1 COMMONWEALTH OF PENNSYLVANIA ss.
COUNTY'OP CHESTER~
G.
R. Rainey, being first duly sworn, deposes and says:
That he is Vice President of Philadelphia Electric Company, that he has read the response to Generic Letter No.
87-02, supplement 1,
" Verification of-Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactore, Unresolved Safety Issue (USI) A-46," and knows the contents thereof; and that-the statements and matters set forth th'-rein; are true.and correct to the best of his knowledge, infor stion and belief.
n K,
44
,?>CrV1ce-Pfedid*ent
/
~
Subscribed and sworn to h
before me this l't ' day of- $gsryk)g/p 1992.
/")
/n
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- ~1?'
//(A MAct-~
' ??R A 4 3
' - No,tary Public Nota:ialSea' Enea A.Sarton,Notwy W TroogonTs,ChesterCourt MyConvrassionEx;rosJuly 10.g995
a
,v s.
ATTACHMENT'1 DESCRIPTION OF LICENSING: BASIS IN STRUCTURE RESPONSE SPECTRA PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 s
Description of Models:
(Ref: PBAPS UFSAR Appendix C and PBAPS Specification G-14)
- Mathematical models consist of stick models containing lumped masses and stiffness coefficients.
- A dynamic analysis using the time history technique was used to generate the In-Structure Response Spectra.
- No Soil Structure Interaction analysis was performed,' since buildings are founded on rock.
- Two percent structural damping was used-in the generation of In Structure Response Spectra.
- The-Reactor Building and Radwaste Building)(contains control room) stick models are shown in Figures 1 and 2, respectively.
Input Motion: (Ref: PBAPS UFSAR Appendix C)
- Design Earthquake: max. horizontal ground acceleration = 0.05g (See Figure 3 for ground response spectrum)
- Maximum Credible Earthquake (MCE or SSE): max. horizontal ground acceleration = 0.12g -(See Figure 4 for ground response.
spectrum)
- The site ground response spcctrum and ' the. time - history spectrum of the July 12, 1952 Taft, California S69E Earthquake-normalized for the. 0.05g Design Earthquake are compared in.
Figure 5 for 2% critical damping since only this was used for developing floor spectrum curves.
- Since some of the points from the time-history spectrum fall below the site response
- spectrum, the-ratio of the accelerations obtained by the spectrum response technique to the accelerations-from the time-history analysis was used'as a multiplying factor to increase the time-history spectrum for the Class I structures as appropriate.
Lt.
In Structure Response Spectra:
- In Structure Responso Spectra were generated for The Design Earthquake _-(0. 05g' ' max -- ground acceleration) l only. The irout motion is. described above.
- SSE-Response Spectra are obtained by multiplying-the Design Earthquake spectral values - by 2.4 ~ (0.12/. 05). Since-higher l
structural damping for SSE is not considered,_the SSE values are very conservative.
- In Structure Response Spectra for 5 percent damping at various locations for the Design Earthquake are listed-below. The building locations were chosen to include areas which are higher than about 40 ft above grade and where significant equipment is located (ie. control room). T:.a Response Spectra must be -increased by a factor of 2.4 to obtain the SSE Response Spectra.
Reactor-Building El 165'-0" N-S/E-W Figure 6
-Reactor Building El 195'-0" N-S/E-W Figure 7 Radwaste Building El 150'-0" N-S Figure 8 Radwaste Building El 150'-0" E-W Figure 9 Radwaste-Building El 1658-0" N-S Figure 10 Radwaste Building El 165'-0" E-W Figure 11 Structure
Response
Spectra are obtained from PBAPS Specification G-14,
" General Project Class I
' Seismic Requirements for Equipment, Instrumentation, Systems and Components for Peach Bottom Atomic Power Station Units 2-& 3 for the Philadelphia Electric Company"
--e LEGEND:
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UPDATED FINAL SAFETY ANALYSl5 REPORT RESPONSE SPECTRA (MAXIMUM CREDIBLE EARTHQUAKE)
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