ML16341D572
| ML16341D572 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 01/08/1986 |
| From: | Schierling H Office of Nuclear Reactor Regulation |
| To: | Shiffer J PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8601210631 | |
| Download: ML16341D572 (18) | |
Text
Docket Nos.:
50-275 and 50-323 January 8, 1986 Mr. J.
D. Shiffer, President Nuclear Power Generation c/o Nuclear Power Generation Company Pacific Gas and Electric Company 77 Beale Street, Room 1451 San Francisco, California 94106
Dear Mr. Shiffer:
SUBJECT'PENT FUEL POOL RERACKING As a result of our ongoing review of your proposed spent fuel pool reracking as described in your letters DCL-85-306 (Reracking Report) and 333(LAR 85-13),
dated September 19 and October 30, 1985, respectively and as discussed in a meeting with you on December 5,
1985 we have determined that additional information is required to complete our evaluation as identified in Enc1'osure 1.
Some of this information was identified during the December 5,
1985 meeting and was summarized in our report dated January 6,
1986.
In order to meet our schedule for completing the evaluation we request that you submit your responses to this request by January 23, 1986.
We will inform you if there are any further requests.
Sincerely,
Enclosure:
As stated cc:
See next page Distribution:
acket File 50-275,323 C
PDR Local PDR PD3 Reading H. Thompson C. Parrish H. Schierling OELD W. Brooks L. Chandler R. Fell H. Gilpin S.
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/s/HSchierling Hans Schierling, Senior Project'Manager PWR Project Directorate No.
3 Division of PWR Licensing-A A. Singh J.
Wing R. Herrick (Franklin)
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Mr. J.
D. Shiffer Pacific Gas and Electric Company Diablo Canyon CC:
Philip A. Crane, Jr.,
Esq.
'acific Gas
&, Electric Company Post Office Box 7442 San Francisco, California 94120 Mr. Malcolm H. Furbush Vice President - General Counsel Pacific Gas
& Electric Company Post Office Box 7442 San Francisco, California 94120 Janice E. Kerr, Esq.
California Public Utilities Comnission 350 McAllister Street San Francisco, California 94102 Mr. Frederick Eissler, President Scenic Shoreline Preser vation Conference, Inc.
4623 More Mesa Drive Santa Barbara, California 93105 Ms. Elizabeth Apfelberg 1415 Cozadero San Luis Obispo, California 93401 Mr. Gordon A. Silver Ms. Sandra A. Silver 1760 Alisal Street San Luis Obispo, California 93401 Harry M. Willis, Esq.
Seymour
& Willis 601 California Street, Suite 2100 San Francisco, California 94108 Mr. Richard Hubbard MHB Technical Associates Suite K
1725 Hamilton Avenue San Jose, California 95125 Mr. John Marrs, Managing Editor San Luis Obis o Count Tele ram Tribune o nson venue P. 0.
Box 112 San Luis Obispo, California 93406 Resident Inspector/Diablo Canyon NPS c/o US Nuclear Regulatory Comnission P. 0.
Box 369 Avila Beach, California 93424 Ms.
Raye Fleming 1920 Mattie Road Shell Beach, California 93440 Joel Reynolds.
Esq.
John R. Phillips, Esq.
Center for Law in the Public Interest 10951 West Pico Boulevard Third Floor Los Angeles, California 90064 Mr. Dick Blankenburg Editor & Co-Publisher South County Publishing Company P. 0. Box 460 Arroyo Grande, California 93420 Bruce Norton, Esq.
Norton, Burke, Berry
& French, P.C.
202 E. Osborn Road P. 0.
Box 10569 Phoenix, Arizona 85064 Mr. W. C. Gangloff Westinghouse Electric Corporation P. 0.
Box 355 Pittsburgh, Pennsylvania 15230 David F. Fleischaker, Esq.
P. 0.
Box 1178 Oklahoma City, Oklahoma 73101
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Pacific Gas 8 Electric Company Diablo Canyon CC:
Arthur C. Gehr, Esq.
Snell 5 Wilmer 3100 Valley Center Phoenix, Arizona 85073 Mr. Leland M. Gustafson, Manager Federal Rel ations Pacific Gas 5 Electric Company 1726 M Street, N.W.
Suite 1100 Washington, DC 20036-4502 Regional Administrator, Region V
U.S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, California 94596 Michael J. Strumwasser, Esq.
Special Counsel to the Attorney General State of California 3580 Wilshire Boulevard, Suite 800 Los Angeles, California 90010 Mr. Tom Harris Sacramento Bee 21st and 0 Streets Sacramento, Cal ifornia 95814 Mr. H. Daniel Nix California Energy Commission 1516 9th Street, MS 18 Sacramento, California 95814 Lewis Shollenberger, Esq.
US Nuclear Regulatory Commission Region V
1450 Maria Lane Suite 210 Walnut Creek, California 94596 Mr. Thomas Devine Government Accountability Project Institute for Policy Studies 1901 gue Street, NW Washington,-
DC 20009
F
Pacific Gas
& Electric Company w 3 Diablo Canyon CC:
Chairman San Luis Obispo County Board of Supervisors Room 220 County Courthouse Annex San Luis Obispo, California 93401 Director Energy"Facilities Siting Division Energy Resources Conservation and Development Commission 1516 9th Street Sacramento, California 95814 President California Public Utilities Commission California State Building 350 McAllister Street San Francisco, California 94102 Mr. Joseph
- 0. Ward, Chief Radiological Health Branch State Department of Health Services 714 P Street, Office Building ¹8 Sacramento, California 95814
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REQUEST FOR ADDITIONAL INFORMATION DIABLO CANYON NUCLEAR POWER PLANT, UNITS I AND 2 SPENT FUEL POOL RERACKING 1.
The information in the Reracking Report reqarding the radioloqical consequences for routine operations and certain accident scenarios is qualitative (e.g.,
page 7-3 regardinq doses; paqe 7-4 regarding filter and resin replacement; page 7-9 reqarding plant man-rem, page 7-15 regarding off-site doses).
Provide a quantitative comparison of the radiological consequences for the existing spent fuel storage and the proposed reracking of the spent fuel pool.
2.
Provide the changes in projected annual doses and plant life doses (increases or decreases) resulting from the proposed rerackina.
3.
Verify that no changes in the plant radiation zoning as identified in the FSAR are necessary as a result of the rerackina.
4.
Verify that, as a result of the rerackina, no chanqes to the ventilation system and fuel pool water cleanup
- system, such as shieldinq, are necessary for radiological reasons.
Verify that the systems as described in the FSAR remain unchanqed.
5.
Regarding ALARA requirements and practices discuss the following:
a.
How the ALARA design review was conducted consistent with Regulatory Guide 8.8..
Discuss the documentation of the review and provide examples.
b.
How the experience of other individuals (non-PGSE) and at other facilities was utilized regarding post-modifications operations with respect to ALARA.
c.
The Diablo Canyon ALARA proqram that will be applied during the spent fuel pool operations.
6.
Verify that spent fuel from other facilities will not be received, shipped or stored at the Diablo Canyon Plant."
7.
Discuss in more detail the features and operation of the spent fuel shipping cask washdnwn area.
8.
Discuss the materials comoatibilitv of the rerack structures with the spent fuel pool water environment.
2 9.
10.
Provide the results of the fuel handling accident analysis.
If the radiological consequences do not change this should be clearly stated and the calculated offsite doses be reported.
The assumptions for the analysis should also be presented.
As discussed at the meeting on December 5, 1985 the backup source cooling water for the spent fuel pool is the condensate storage tank and the fire water tank.
Evaluate the amount of water required in these tanks to meet both the ESF needs during a plant emergency and at the same time provide the makeup for evaporation losses from the spent fuel pool in the event of the loss of normal cooling.
Evaluate the plant technical specifications to assure that the necessary water level is maintained to accommodate both uses.
The rack module desiqn criteria are based upnn Section 3.8.4, Appendix D, of the NRC's Standard Review Plan.
The staff requires that load combin-
ations and allowable stresses for spent fuel rack modules be in accordance with the allowable values of the NRC's Position Paper, "OT Positinn for Review and Acceptance of Spent Fuel Storaae and Handlinq Applications,"
U. S. Nuclear Regulatorv Commission, January 18, 1979.
Demonstrate that the modules meet the OT Position criteria.
12.
13.
14.
15.
Because of the added nonlinear complexity associated with the increased number of gap elements in the three-dimensional displacement analysis to account for rack-to-rack impact, the rack displacement analysis is based upon an 8 degree-of-freedom (DOF) model.
Provide documentation showing the following:
That the 8 DOF model adequately portrays the mass-elastic dynamic motion of the fuel rack module (such as comparison of maximum displacement and time of recurrence with 32 DOF models).
a ~
b.
How the sinqle lumped mass represents the movement of the fuel assemblies and how it is referred to the top of the model.
c.
How convergence and stability of the numerical integration on the nonlinear displacement solution are assured.
Describe the analysis methodoloay used to determine stresses in the rack module hase metal and welds due to impact hetween the support pads and the floor followinq liftoffand due to rack-to-rack lateral impact.
Justify the selection of the 6 x ll cell rack module, stated tn have the largest aspect ratio, for the presentation of the analysis results.
Include a discussion of why the natural frequencies of other racks would not make them more susceptible to large displacements under seismic excitation.
Mith respect tn the spent fuel structure only limited information is provided in the Reracking Report regarding the adequacy of the analytical procedures, the load combination criteria, or the selection nf allowable
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Accordinqly, the staff requests that you provide the following:
a.
Sketches and/or drawings of any changes to the spent fuel pool structure not considered in the FSAR analysis.
b.
A description of the mathematical model of the pool structure, including the finite-element model, if used, and the method of analysis.
Describe the assumptions employed and the limitations of the model.
c.
A detailed description of the loadinqs
- used, and justification for the load combination.
d.
Identification of the source of the acceptance criteria and method of determininq the allowable loads and stresses in various parts of the structure.
e, Description of the dynamic interaction between the pool structure and the rack modules, including the value of any dynamic amplifi-cation factors.
Include all assumptions made regarding the sumation and phase of all rack module dynamic loads.
. f An analysis of the adequacy of the pool floor and liner under rack slidinq and impact loads.
q.
Identification of the critical regions of the pool structure.
List the loads or stresses as appropriate.
Compare the loads and/or stresses to allowable values, indicatinq the source of the allowable in. accordance with Item 15.d above.
16.
Discuss the spent fuel pool cooling system with respect to the require-ments of General Desiqn Criterion 44 of 10 CFR 50, Appendix A.
17.
The Reracking Report does not include the calculated decay heat loads for the proposed pool modifications or sufficient information for the staff to calculate the loads independently.
Provide the following information (a) all anticipated future discharqes as a function of decay time and (b) the decay heat load for each discharae for the maximum normal and the maximum abnormal conditions (the maximum normal heat load is the heat load assuming the pool is filled with successive normal refueling discharges; the maximum abnormal heat load is the heat load assuming one full core discharge and successive normal refuelinq discharges).
18.
Provide the time interval between reactor shutdown and the commencement of the discharge of assemblies.
Provide the time to comolete a normal discharge and a full core discharge.
19.
Provide a
P8 I diaqram of the spent fuel pool coolinq system, and provide the assumptions made in establishing its rated heat removal capability.
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20.
For the maximum normal and maximum abnormal heat load conditions pro-c vide the pool water temmperature as a function of time -and all assumptinns on which the calculations are based.
21.
For the maximum normal and maximum abnormal heat loads, assuminq the pool coolino is lost, provide the time before boilinj occurs, the boiloff
- rate, and the time before the boiloff causes the top of the storage racks to become uncovered.
22.
Describe the pool water level monitoring system and indicate the location of the alarm.
23.
Describe the available makeup water systems, the quantity available from each source, and their seismic classification.
Indicate their respective makeup rates and the time interval between their activation and when the makeup flow rate is achieved.
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January 8, 1986 ON cket" File o encl.
g w/o encl.
CVogan w/encl.
H.Schierling w/encl.
DOCKET NO(S).50-275 and 50-323 Nr. James D. Shiffer Vice President of Nuclear Power Generation Pacific Gas and Electric Company 77 Beale Street - Boom 1451 San Francisco, Cal ifornia 94106
SUBJECT:
DIABDO CANYON NUCLEAR POllER PLANT UNITS 1
AND 2 The following documents concerning our review of the subject facility are transmitted for your information.
4
(
O Notice of Receipt of Application, dated O Draft/Final Environmental Statment, dated O Notice of Availabilityof Draft/Final Environmental Statement, dated O Safety Evaluation Report, or Supplement No.
, dated O Notice of Hearing on Application for Construction Permit, dated O Notice of Consideration of Issuance of Facility Operating License, dated O Monthly Notice; Applications and Amendments to Operating Licenses Involving no Significant Hazards Considerations, dated O Application and Safety Analysts Report, Volume O Amendment No.
to Application/SAR dated O Construction Permit No. CPPR-
, Amendment No dated
, dated O Facilit Operating License No.
, Amendment No.
O Order(Extending Construction Completion Date, dated KI Other(SpecifyJ Dated Januar 6, 1986 RE; S ent Fuel Stora e Rerackin 4l
Enclosures:
As stated Division.of PHR. Licensina-A.
uftice ot Nuclear%eactor ttegalation CC:
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NRC FORM 318 (1/84) NRCM 0240
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