ML20056G275
| ML20056G275 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/17/1993 |
| From: | Eaton R Office of Nuclear Reactor Regulation |
| To: | Boulette E BOSTON EDISON CO. |
| References | |
| TAC-M85898, NUDOCS 9309020345 | |
| Download: ML20056G275 (5) | |
Text
I August 17, 1993 Docket No. 50-293 Mr. E. Thomas Boulette, Ph.D Senior Vice President - Nuclear Boston Edison Company Pilgrim Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts 02360
Dear Mr. Boulette:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - PILGRIM NUCLEAR POWER STATION -
INCREASE ALLOWED FUEL ASSEMBLY STORAGE (TAC N0. M85898)
On February 11, 1993, Boston Edison submitted an application to amend the Technical Specifications {TS) for Pilgrim Nuclear Power Station.
The proposed change would revise the TS to increase allowed fuel assembly storage.
In order to complete our review from the standpoint of structural adequacy, please provide the information requested in the enclosure.
If you need i
clarification on this request, please call me on (301) 504-3041.
The requirements of this letter affect fewer than 10 respondents, and, therefore, are not subject to the Office of Management and Budget review under i
P.L.96-511.
Sincerely, Original signed by:
Ronald B. Eaton, Senior Project Manager Project Directorate 1-3 Division of Reactor Projects - I/II j
Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information
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cc w/ enclosure:
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'%f August 17, 1993 i
Docket No. 50-293 l
Mr. E. Thomas Boulette, Ph.D Senior Vice President - Nuclear Boston Edison Company Pilgrim Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts 02360
Dear Mr. Boulette:
l
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - PILGRIM NUCLEAR POWER STATION -
INCREASE ALLOWED FUEL ASSEMBLY STORAGE (TAC N0. M85898)
J On February 11, 1993, Boston Edison submitted an application to amend the Technical Specifications (TS) for Pilgrim Nuclear Power Station.
The proposed i
change would revise the TS to increase allowed fuel assembly storage.
In l
order to complete our review from the standpoint of structural adequacy, j
i please provide the information requested in the enclosure.
If you need clarification on this request, please call me on (301) 504-304).
The requirements of this letter affect fewer than 10 respondents, and, therefore, are not subject to the Office of Management and Budget review under l
P.L.96-511.
Sincerely,
/
i 1
l onald B. Eaton, Senior Project Manager Project Directorate I-3 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation l
Enclosure:
Request for Additional Information l
cc w/ enclosure:
l See next page l
l
Mr. E. Thomas Boulette Pilgrim Nuclear Power Station cc:
Mr. Edward S. Kraft, Mr. H. Vernon 0heim Vice President of Nuclear Manager, Reg. Affairs Dept.
Operations & Station Director Pilgrim Nuclear Power Station Pilgrim Nuclear Power Station RFD #1 Rocky Hill Road RFD #1 Rocky Hill Road Plymouth, Massachusetts 02360 Plymouth, Massachusetts 02360 Mr. David F. Tarantino Resident Inspector Nuclear Information Manager U. S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station Pilgrim Nuclear Power Station RFD #1, Rocky Hill Road Post Office Box 867 Plymouth, Massachusetts 02360 Plymouth, Massachusetts 02360 Mr. Thomas Rapone Chairman, Board of Selectmen Secretary of Public Safety 11 Lincoln Street Executive Office of Public Safety Plymouth, Massachusetts 02360 One Ashburton Place Boston, Massachusetts 02108 Office of the Commissioner Massachusetts Department of Mr. David Rodham, Director Environmental Protection Massachusetts Emergency Management One Winter Street Agency Boston, Massachusetts 02108 400 Worcester Road P.O. Box 1496 Office of the Attorney General Framingham, Massachusetts 01701-0317 One Ashburton Place Attn: James Muckerheide 20th Floor Boston, Massachusetts 02108 Chairmen, Citizens Urging Responsible Energy Mr. Robert M. Hallisey, Director P. O. Box 2621 Radiation Control Program Duxbury, Massachusetts 02331 Massachusetts Department of Public Health Citizens at Risk 305 South Street P. 3. Box 3803 Boston, Massachusetts 02130 Plymouth, Massachusetts 02361 Regional Administrator, Region I W. S. Stowe, Esquire U. S. Nuclear Regulatory Commission Boston Edison Company 475 Allendale Road 800 Boylston St., 36th Floor King of Prussia, Pennsylvania 19406 Boston, Massachusetts 02199 Mr. Paul J. Hamilton Licensing Division Manager Boston Edison Company 25 Braintree Hill Park Braintree, Massachusetts 02184 L-
~
i Enclosure RE00EST FOR ADDITIONAL INFORMATION PROPOSED RERACKING l
PILGRIM NUCLEAR POWER STATION. UNIT 1 1.
In criterion (iv) of Section 3.1, it is stated, "the configuration of welding is designed to 'detune' the racks from the ground motion such that the rack displacemeists are minimized." Provide a discussion of how 4
this objective is accomplished in the existing as well as the new racks.
2.
In Section 3.4a, three design codes (specifications) are listed as being used for the design and fabrication of the new racks; vir, (1) AISC Manual - 1980, (2) ASME B & PV Code,Section III, Div.1 - 1986, and (3) ANSI /AISC N690 - 1984.
Provide information on how these three design codes are utilized in the design and fabrication of the rack components.
[
3.
In the discussion of " fluid coupling" under Section 6.2, it is stated,
" Subsequently laboratory experiments were conducted to validate the multi-rack fluid-coupling theory." Provide information related to these experiments, and discuss how the Fritz's two-body fluid-coupling model was extended to be applicable to the multi-body applications.
4.
Please provide the digitized version of the controlling set (i.e.,1.15 x set 2) of time-histories in three orthogonal directions used for the seismic analysis of racks (on a 31/2" diskette).
5.
Provide the procedure used to determine the lateral impact load capacity l
of the cell walls (i.e., 3510 lbs). Also provide the procedure used to determine the cell-wall it.tegrity under (1) biaxial bending -
generalized rack bending and localized bending under hydro-dynamic pressure on the exterior cell walls, (2) compressive buckling of l
internal cell walls in the horizontal direction due to hydro-dynamic fluid pressures on the two opposite sides of an interior rack.
6.
Provide an assessment of stresses at the seam weld in the cell under the J
worst condition of the postulated seismic loading.
7.
Provide a schematic of whole-pool-multi-rack (WPMR) model showing the racks and the gap elements indicated in Table 6.8-2.
8.
During the implementation of Campaign I, the N2 and E6 racks are likely to undergo larger displacements than the ones shown by the analysis with all racks in the spent fuel pool (SFP). By utilizing the WPMR analysis, demonstrate that:
(1) individually they will meet the staff's provision l
against overturning in Standard Review Plan 3.8.5, and (2) they will not impact each other at the corners.
l l
i
- 9.
In Section 8.4.3, Reference 8.1.2 (ACI 349-85) has been used to arrive at the controlling factored load combinations.
It should be noted that the ACI 349-76 has been endorsed by the NRC in Regulatory Guide (RG) 1.142, " Safety-Related Concrete Structures for Nuclear Power Plants."
The RG recommends a load factor of 1.9 for operating basis earthquake (0BE). Provide information on how the increased load factor (from 1.7 to 1.9) for the OBE would change the results of the analysis of the SFP structure and the supporting structures.
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