ML20106A570
| ML20106A570 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/21/1992 |
| From: | Broughton T GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR C311-92-2119, GL-87-02, GL-87-2, NUDOCS 9209290098 | |
| Download: ML20106A570 (5) | |
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ENuclear cYat:U r""
Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2383 Vw'er's Direct Dial Numoer:
j (717',948-3005 September 21, 1992 C311-92-2119 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 o
Gcatlemen:
Subject:
Three Mile Island Nuclear Generating Station (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Response to Supplement I ta Generic Letter 87-02 SQUG Resolution of USI A-46 Gii February 10, 1987, the NRC issued Generic Letter 87-02, " Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety issue (UCI) A-46".
Inis Ger eric Letter encouraged utilities to participate in a generic program to resolve the seism.c verification issues associated with USI A-46.. As a rasult, the Seismic Qvalification Utility Group
("SQUG") developed the " Generic Implementation Procedure (GIP) for-Seismic Verification of Nuclear Plant Equipment". On May 22, 1992, the NRi, Staff issued Generic Letter 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, Revisit;n 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, the following information.
By letter dated August 21, 1992, to James G. Partlow, NRR-NRC, SQUG clarified that the 120 days would expire on' September 21, 1992.
This letter cesponds to the Staff's mquest, NRC RE0VESI:
p A statement whether you commit to sse both the SQUG commitments and the Em implementation guidance provided in GIP-2 as supplemented by the SSER No. 2 for the resolution of USI A-46.
In this case, any deviation from GIP-2, as to supplemented by the SSER No. 2, must be identified, justified, and documented.
_08 If you do not make such a commitment, you must provide your alternative for
'o responding to GL 87-02.
ins:
oI$ D GPU NUCLEAR RJSPONSE:
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As a member of SQUG, GPU Nuclear commits to use the SQUG methodology as 06 f
om documented in the GIP, where " GIP" refers to GIP Revision 2, corrected on I
I February 14, 1992, to resolve USI A-46 at TMI-1.
The GIP, as evaluated by the l,
Staff, permi S licensees to deviate from the SQUG commitments embodied in the
' ' : Nuclear Corporaben is a subsid;ay of General Pubhc Unht es Corporabon
- C311-92-2119 Page 2 Comitmant' sections, provided the Staff is notified of substantial deviations prior to implementation.
GPU Nuclear 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
- deviation from the provisions of" Generic letter 87-02.-
Specifically, GPU Nuclear hereby comits to the SQUG commitments set forth in the GIP, including the clarifications, interpretations, and exceptions identified in SSER-2 as clarified by the August 21, 1992, SQUG letter responding to SSER-2 with the following clarification.
Verification of the Riqid Ease Plate The SSER No. 2 states that the rigid baseplate assumption.should-be-e verified prior to using the ANCHOR Code (Ref. SSER No. 2 - Section 11.4.4 No. 9). We have contacted the program's author, Stevenson-& Associates, and they assert that the ANCHOR code is not formulated using a rigid _ _
baseplate assumption. We were informed by Stevenson & Associates that EPRI/SQUG is transmitting this information generically.
With respect to the GIP implementation guidance, GPU Nuclear generally will be guida by the remaining (non-commitment) sections of the GIP, i.e., GIP implementation guidance, which comprises suggested methods for implementing the applicable commitments.
GPU Nuclear will notify the NRC as soon as practicable, 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.
NRC RE0 VEST:
A plant-specific schedule for the implementatio. of the GIP and submission of a report to the staff that summarizes the results of the USI A-46 review, if you are committing to implement GIP-2.
This schedule shall be such that each affected plant will complete its implementation and submit the summary report within 3 years after the issuance of the SSER No. 2, 'unless otherwise justified.
[fy NUCLEAR RESPONSE:
Our evaluttion of overall Integrated Schedule activities and assessment of the status of the USI A-46 and IPEEE efforts for. THI-1 and Oyster Creek Nuclear Generating Station has indicated that sufficient resources are available and can be allocated to support completion and submittal of the results of the TMI-
-I USI A-46 review by May 22, 1995, within three (3) years after the issuance of the SSER No. 2.
NRC REQUESI:
The detailed information as to what procedures and criteria were used to generate the in-structure response spectra to be used for USI A-46 as requested in the SSER No. 2.
The licensee's in-structure response spectra are considered acceptable for USI A-46 unless the staff indicates otherwise during a 60-day
' review period.
C311-92-2119 Page 3 CPU NUCLLAS_RISPONSD for defining seismic demand, GPU Nuclesr will use the options provided in the GIP for median-centered and conservative design in-structure response spectra, as appropriate, depending on the building, the location of equipment in the building and characteristics of the specific piece of equipment. When the most appropriate option involves the use of SSE in-structure-response spectra, GPU Nuclear intends to use either of the alternatives described below:
L The licensing basis SSE response spectra as described in Sections 5.2.4 and 5.4.4 of the Three Mile Island Unit 1 FSAR.
These spectra were developed using the method developed by Biggs and Roesset as described in Reference 1.
The ground response spectra used as input to the analysis was a composite of records from the March 1957 San francisco earthquake and the 1940 E; Centro earthquake and was' l
anchored at 0.129 for SSE, Details of the methodology used to develop the ground response spectra are described in Sections 2.7.1 and 2.8 of the Three Mile Island Unit 1 FSAR.
2.
New in-structure response spectra to be developed, as discussed in Section 4.2.4 of the GIP, for use in the reso;ution of USI A-46.
These spectra will be develcped consistant with standards and guidance given in the NRC's Standard Review Plan.
The detailed procedures and criteria to be used to generate the spectra will be submitted to the Commission when they become available as required in l
Section II, 4.2.3 of the Staff's SSER, Pending timely completion of the Staff's review of the new spectra, GPU Nuclear still plans to complete resolution of V51 A-46 in accordance with the schedule provided in this letter.
l-GPU Nuclear considers both of the spectra described above to be conservative design response spectra as defined on Page 4-18 of the GIP-2.
If you have any questions concerning the information provided in this letter,-
please call Mike Laggart, Manager, Corporate Licensing, at (201) 316-7968.
Sincerely,
(
[c h b
l T.G.Broughton l
Vice President and Director, THI-l YN:lga Attachment cc:
Region I Administrator THI Senior Resident Inspector THI-l Senior Project Manager r
C311492-2119 ATTACHMENT t
BEEBWEE:
1.
J. M Biggs and J. M. Roesset, " Seismic Analsis of Equipment Mounted on a Massive Structure", Seminar on Seismic Design of Nuclear Power Plants, Massachusetts Institute of Technology, v
e m
C311-92-2119 METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GENERAL PUBLIC UTILITIES NUCLEAR CORRORATION Three Mile Island Nuc'. ear Station, Unit 1 (THI-1)
Operating License No. DPR-50 Docket No. 50-289 Response to Generic Letter 87-02, Supplement 1 Seismic Qualification Utility Group (SQUG) Resolution of USI A-46 This letter is submitted in response to Supplement I to Generic Letter 87-02, Seismic Qualification Utility Group (SQUG) Resolution of USl A-46.
All statements contained in this response have been reviewed and all such statements made and matter set forth therein are true and correct to the best of my knowledge.
O~
T. G. Brought /n Vice President and Director, THI-l D
Signed and sworn before me this 22nd day of September
, 1992.
MRL$obbL Kn S h Not'ary Public
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