ML20196K904
| ML20196K904 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/31/1999 |
| From: | Lochbaum D AFFILIATION NOT ASSIGNED |
| To: | |
| Shared Package | |
| ML20196K880 | List: |
| References | |
| 99-762-02-LA, 99-762-2-LA, LA, NUDOCS 9904080128 | |
| Download: ML20196K904 (24) | |
Text
,
. EXHIBIT 4 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISISON Before the ATOMIC SAFETY AND LICENSING BOARD In the matter of )
)
CAROLINA POWER & LIGHT COMPANY ) Docket No. 50-400
)
(IIarris Nuclear Plant) ) March 31,1999 DECLARATION OF DAVID A. LOCHBAUM. NUCLEAR SAFETY ENGINEER.
UNION OF CONCERNED SCIENT.lSTS. CONCERNING TECHNICAL ISSUES AND SAFETY MATTERS INVOLVED IN THE HARRIS NUCLEAR PLANT LICENSE AMENDENT FOR SPENT FUEL STORAGE l I, David A. Lochbaum, make the following declaration:
l 1. My name is David A. Lochbaum. I reside in the state of Maryland.
l
- 2. I am employed by the Union of Concerned Scientists as its nuclear safety engineer. I have been so employed since October 1996. I have the following responsibilities: a) direct and coordinate UCS's nuclear safety program; b) monitor developments in nuclear industry to assess and respond to impact; c) serve as technical authority and spokesperson on nuclear issues; and d) initiate legal action to correct safety problems.
- 3. The Union of Concemed Scientists, with offices located at 1616 P Street NW Suite 310, Washington, DC 20036, is an indenendent nonprofit organization dedicated to advancing responsible public policies in areas where technology plays a critical role.
9904000128 990405 PDR ADOCK 05000400 0 PDR -
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Declaration ofDavid A. Lochbaum, Nuclear Jafety Engineer Page2
- 4. I have worked in the field of nuclear engineering since June 1979. I am a graduate of the University of Tennessee with a bachelor of science in nuclear engineering.
- 5. After receiving my nuclear engineering degree, I went to work for the Georgia Power Company as ajunior engineer at their Edwin 1. Hatch Nuclear Power Plant. I held various positions in the commercial nuclear power industry over the next 17 years prior to joining UCS. This experience is detailed in the resume attached hereto as Exhibit A.
- 6. I am the author of Nuclear Waste Disposal Crisis (Pennwell Books, Tulsa, January 1996) on the technical problems with spent fuel storage at reactor sites.
/. I have examined the license amendment application dated December 23,1998, submitted by the Carolina Power & Light Company (CP&L) to the Nuclear Regulatory
!. Commission (NRC) concerning spent fuel storage at the Harris Nuclear Plant and the report prepared by Gordon Thompson of the Institute for Resource and Security Studies titled," Risks and Alternative Options Associatr with Spent Fuel Storage at the Shearon 1
Harris Nuclear Power Plant," dated February 1999. I am familiar with these documents and have relied upon them in formulating the opinions contained in this declaration. I I have also examined and am familiar with, for the purposes of preparing this declaration, the applicable federal regulations contained in Title 10 of the Code of Federal
! Regulations; NRC Information Notice No. 85-30: "Microbiologically Induced Corrosion of Containment Service Water System," dated April 19,1985; NRC Information Notice No. 85-56: " Inadequate Environment Control For Components and Systems in Extended Storage or Layup," dated July 15,1985; NRC Information Notice No. 94-38: "Results of
- Declaration ofDavid A. Lochbaum, Nuclear Safety Engineer Page 3 a Special NRC Inspection at Dresden Nuclear Power Station Unit 1 Following a Rupture
)
of Service Water Inside Containment," dated May 27,1994; NRC Inspection Manual Procedure 92050: " Review of Quality Assurance For Extended Construction Delay;"
NRC Inspection Report No. 50-400/80-26,50-401/80-24,50-402/80-24, and 50-403/80-24, dated January 2,1981; letter from Darrell G. Eisenhut, Nuclear Regulatory '
Commission, to Christopher John Adams, The Orange County Democratic Party, dated June 9,1981; NRC Inspection Report No. 50-400/81-14,50-401/81-14,50-402/81-14, .
and'50-403/81-14, dated August 5 (or 25*),1981; NRC Inspection Report No. 50-400/81-13,50-401/81-13,50-402/81-13, and 50-403/81-13, dated August 13,1981; and NRC Inspection Report No. 50-400/81-15,50-401/81-15,50-402/81-15, and 50-403/81-15, dated September 14,1981. I have also relied upon these documents in formulating my opinions as expressed in this declaration.
- 8. Having examined the relevant documents as mentioned above, it is my professional opinion that CP&L's proposed use of an alternative plan per 10 CFR 50.55a to demonstrate that the Unit 2 fuel pool cooling system was " designed, fabricated, erected, constructed and inspected to quality standards commensurate with the importance of the safety function to be performed"' raises significant safety concerns for persons living near the facility. It is also my professional opinion that these significant safety concerns have not been adequately considered in the license amendment application filed by CP&L. These concerns are set forth below. I recommend that they be
' 10 CFR 50.55a, Codes and standards.
h*
l V
Declaration ofDavid A. Lochbaum,' Nuclear Safety Engineer Page 4 included in the subject matter of issues to be considered by the Atomic Safety and Licensing Board in the above captioned proceeding.
- 9. It is my professional opinion that the Alternative Plan, as described in Enclosure 8 l
l to the December 23, 1998, license amendment application submitted by CP&L, is 1
deficient for the following reasons:
(a) CP&L notified the NRC in December 1981 that construction on Units 3 and 4 at the IIarris Nuclear Plant had been cancelled. In December 1983, CP&L notified the NRC l that Unit 2 had been cancelled. Unit I was completed and placed into commercial
. operation in May 1987.2 (b) The Alternative Plan describes the process CP&L proposes to certify the installed portions of the Unit 2 spent fuel pool cooling system at the Harris Nuclear Plant in lieu of the original construction records which purportedly were discarded in Septemb'er 1993.3 (c ) The Alternative Plan includes review of available documentation, inspection and/or examination of accessible components, internal (via camera) inspections of selected inaccessible components, and hydrostatic testing.
(d)' The Altemate Plan and the license amendment application do Dol describe any program for proper storage and preservation of materials and components as required by Appendix B to 10 CFR Part 50. Nor do they describe any effort to determine if the installed piping and equipment experienced any deterioration over the many years of non-use since the piping and equipment were installed.
I I
l
' CP&L, Enclosure 8 to December 23,1998 submittal, pp.1-2. !
8 CP&L, Enclosure 8 to December 23,1998 submittal, page 11.
I i
Declaration ofDavid A. Lochbaum. Nuclear Safety Engineer Page5 (e) NRC Information Notice No. 85-30 documents a problem experienced at the H B Robinson nuclear plant, also owned and operated by CP&L, during 1984. According to this NRC document, stainless steel piping at the Robinson plant experienced significant corrosion pitting during an outage lasting about one year.
(f) The NRC issued Information Notice No. 85-56 "to alert addressees to problems which can occur if equipment is improperly stored or laid up during construction or 4
extended plant outages. Addressecs also are reminded that programs for proper storage and preservation of materials and components are required by NRC regulations (10 CFR 50, Appendix B), even though not specifically addressed as license conditions."
l According to this NRC document, a heat exchanger at Nine Mile Point Unit 2 was found to have experienced significant corrosion in the eight (8) years it had been stored in-place.
(g) NRC Infonnation Notice No. 94-38 documents a problem at Dresden Unit 1. A water-filled pipe froze and ruptured, causing 55,000 gallons'of water to flood the containment building. The NRC reported that the plant's owner had not taken adequate measures to prc. -t the permanently closed facility. The NRC also reported that had a water-filled pi} < wnnected to the spent fuel pool- which was as unprotected as the pipe which failed - ruptured, the water level in the spent fuel pool could have dropped below l l
the top ofits irradiated fuel assemblies.
(h) NRC Inspection Procedure 9.'350 contains guidance for NRC inspectors when auditing nuclear plants encountering extended construction delays. Among other areas, j I
l
Declaration ofDavid A. Lochbaum, Nuclear Safety Engineer Page 6 the guidance covers the plant owner's program foi a.e protection and preservation of equipment. The elements of this program include:
- 1. Protedive coverings and coatings,
- 2. Internal preservation,
- 3. Dunnage and other supports, and'
- 4. Cleanliness preservation.
The Alternative Plan does not address any of these elements or describe measures taken to protect piping and components during the extended delay between construction and proposed use of this equipment.
- 10. NRC Inspection Report 50-400/80-26,50-401/80-24,50-402/80-24, and 50-403/80-24, dated January 2,1981, transmitted a Notice of Violution to CP&L involving
failure to store equipment in accordance with instructions to prevent damage or deterioration."
- 11. NRC Inspection Report 50-400/81-14,50-401/81-14,56-402/81-14, and 50-403/81-14, dated August 5 (or 25*),1981, transmitted a Notice of Violation to CP&L inv4 !ng " failure to provide records ofinspection and monitoring or work performance."
- 12. NRC Inspection Report 50-400/81-13,50-401/81-13,50-402/81-13, and 50-403/81-13, dated August 13,1981, transmitted a Notice of Violation to CP&L involving
" Inadequate Measures to Control Preservation of Safety Related Materials and Equipment."
E ,
Declaration ofDavid A. Lochbaum, Nuclear Safety Engineer Page l 13. NRC Inspection Report 50-400/81-15,50-401/81-15,50-402/81-15, and 50-l 403/81-15, dated September 14,1981, transmitted n Wtice of Violation to CP&L involving " failure to' follow procedure for inspection of fuel pool liner welding."
- 14. The Altemative Phn, at best, provides assurance that the condition of the Unit 2 l
spent fuel pool cooling system when the facility was cancelled in December 1983 satisfied the quality standards specified in 10 CFR 50.55a. The NRC inspection reports cited in paragraphs 11 and 13 suggest that these quality standards may not have been met in December 1983. In any case, the Altemative Plan provides no assurance that the spent fuel pool cooling system has not deteriorated since that time. Th: NRC inspection reports cited in paragraphs 10 and 12 suggest that CP&L had problems protecting against deterioration before Unit 2 was cancelled. In addition, the Altemative Plan contains no provisions to verify that deterioratio*: has not occurred.
l
- 11. Nuclear industry experience, as evidence by the cited NRC documents, clearly indicates that installed equipment can deteriorate ifnot properly maintained. CP&L proposes to use the Unit 2 spent fuel pool cooling system to remove the decay heat from i
irradiated fuel- a vital safety function that cannot be performed using only the Unit I spent fuel pool cooling system. Thus, it is my professional opinion that the failure of the i
Altemative Plan to provide reasonable assurance against possible deterioration of the j 1
installed Unit 2 spent fuel pool cooling system represents a undue challenge to the i i
proposed use of this system. )
1
- 12. Because it is my professional opinion that the safety concerns addressed in this declaration would be created by the proposed activation the Unit 2 spent fuel pool l l
4 l
l Declarztlon ofDavid A. Lochbaum. Nuclear Safety Engineer Pages cooling system at the Harris Nuclear Plant, I am also of the professional opinion, and do so state here, that the risk to the general public could be increased by the propesed activity, and that the risks and potential are foreseeable, not highly speculative, and potentially significant. 'Iherefore, they should be taken very seriously.
I declare under penalty of perjury that the foregoing facts are true and correct to the best of my knowledge, and the foregoing opinions are based as my best professional judgement.
Executed March 31,1999.
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' David A. [5h%
i l
Exhibit A: Resume of David A. Lochbaum Experience Summary l
10/96 to date Nuclear Safety Engineer, Union of Concerned Scien:ists k I
Responsible for directing UCS's nuclear safety program, for monitoring developments in the nuclear industry, for serving as "le organization's spokesperson on nuclear safety issues, and for i l
initiating action to correc' safety concerns.
l 11187 to 09/96 Senior Consultant, Enercon Services, Inc.
Responsible for developing the conceptual design package for the ahernate decay heat removal system, for closing out partially implemented modifications, reducing the backlog of engineering items, and providing training on design and licensing bases issues at the Perry Nuclear Power Plant.
Responsible for developing a topical report on the station blackout licensing bases for the Connecticut Yankee plant.
Responsible for vertical slice assessment of the spent fuel pit cooling system and for confirmation of licensing commitment implementation at the Salem Generating Station.
Responsible for developing the primary containment isolation devices design basis document, reviewing the emergency diesel generators design basis document, resolving design document ;
open items, and updating design basis documents for the James A. FitzPatrick Nuclear Power Plant. ;
Responsible for the design review of balance of plant systems and generating engineering calculations to support the Power Uprate Program for the Susquehanna Steam Electric Station. i Responsible for developing the reactor engineer training program, revising reactor engineering technical and surveillance procedures and providing power manuevering recommendations at the llope Creek Generating Station.
Responsible for supporting the lead BWR/6 Technical Specification Improvement Program and preparing licensing submittals for the Grand Gulf Nuclear Station.
03/87 to 08/87 System Engineer, General Technical Services Responsible for reviewing the design of the condensate, feedwater and raw service systems for safe shutdown and restart capabilities for the Browns Ferry Nuclear Plant.
08/83 to 02/87 Senior Engineer, Enercon Services, Inc.
Responsible for performing startup and surveillance testing, developing core monitoring software, developing the reactor engineer training program, and supervising the reacter engineers and Shift Technical Advisors at the Grand Gulf Nuclear Station. i
Exhibit A: Rruma cf David A. Lochbaum Experience Sununary (continued) 10181 to 08/83 Reactor Engineer / Shift Technical Advisor, Tennessee Valley Authority Responsible for performing core management functions, administering the nuclear engineer training program, maintaining ASME Section XI program for the core spray and CRD systems, and covering SI'A shifts at the Browns Ferry Nuclear Plant.
06/81 to 10/81 BWR instructor, General Electric Company Responsible for developing administrative procedures for the Independent Safety Engineering Group (ISEG) at the Grand Gulf Nuclear Station. 4 01/80 to 06/81 Reactor Engineer / Shift Technical Advisor, Tennessee Valley Authority Responsible for directing refueling floor activities, performing core management functions, maintaining ASME Section XI program for the RHR system, providing power manuevering recommendations and covering STA shifts at the Browns Ferry Nuclear Plant.
06/79 to 12179 Junior Engineer, Georgia Power Company Responsible for completing pre-operational testing of the radwaste solidification systems and developing design change packages for modifications to the liquid radwaste systems at the Edwin I. Ilatch Nuclear Plant.
Educaron June 1979 Bachelor of Science in Nuclear Engineering, 'Ihe University of Tennessee at Knoxville May 1980 Certification, Interim Shift Technical Advisor, TVA Browns Ferry Nuclear Plant April 1982 Certification, Shift Technical Advisor, TVA Browns Ferry Nuclear Plant Professional AfTiliations Member, American Nuclear Society (since 1978).
f SR/CNEAF/96-01
, c-Spent Nuclear Fuel Discharges from U.S. Reactors 1994 I
I EXHIBIT 5 i
February 1996 l
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Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels Analysis and Systems Division U.S. Department of Energy Washington, DC 20585
~ ' Service Reports are prepared by eta upon special request and may be based on assumption specified by the requestor. Information regarding the request for this report is included m
7 f~
Complimentary subscriptions and single issues are available to certain groups of subscribers, such as public and academic libraries, Federal, State, local and foreign governments, EIA survey respondents, a the media. For further information and for answers to questions on energy statistics, please contact EIA's National Energy Information Center. Address, telephone numbers, and hours are as follows:
National Energy information Center, El-231 Energy information Administration Forrestal Building, Room IF-048 Washington, DC 20585 (202) 586-8800 (202) 586-0727 (FAX)
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Releaseri for Printing: February 9,1996 Printed with soy ink on recycled paper enum e
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Figure 1. Pool Capacities and Inventories for Boiling-Water Reactors (Assemblies)
Bri Rock Point , ,
Browns Ferry 1 & 2 l l Browns Ferry 3 l l l l ',t31993 Pool Storage Total i i Q1994 Discharges and Reinsertions 4 e Brunswick 2 e i , QMaxnnum Estabhshed Storage Capacity
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- - BWR Assemblies Notes: Otta includes all boiling water reactors (BWR's) reported on the Form RW-859. Number of 1994 Discharges and Reinsertions does not include intrautihty transfers See Table 2. Values of 1994 Discharges and Reinsertions for Limerick 1 & 2 and Shoreham reflect the transfer of 254 assernbliestrom Shoreham to Limerick 1 in 1994. See Technical Note 14 in Appendix E.
Source: Energy information Administraton, Form RW-859," Nuclear Fuel Dats"(1994).
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m PWR Assemblies Notes: Data includes ah pressurizedwater reactors (PWRs) reported on the Form RW-not inciude intrautility transfers. See Table 2.
Source: Eriergy information Administration, Form RW-859," Nuclear Fuel Data" (1994).
11
. .... ..i- a ,e-va.,rselon I Soent Nuclear Fuel Discharges from U.S. Reactors 1994
Table 3. Temporarily Discharged Assemblies Temporarily Discharged Assemblies Reactor Pool Site Through Through increasel Electric Utility Name Reactor Name Type ID 1994 1993 Reduction Arizona Public Service Comoany Palo Verde 3 PWR 0303 1 1 0 Car a er and Light Company . Brunswick 1 BWR 0701 1 1 0 Cleveland Electric illuminating Company Perry 1 BWR 0901 0 4 -4 Consolidated Edison Company of New York Indian Poir,t 2 PWR 1102 8 i 8 0 Consumers Power Company . . Big Rock Point BWR 1201 1 0 1
! Palisades PWR 1204 1 1 0 Detroit Edison Company . Enrico Fermi 2 BWR 1402 40 40 0 Duquesne Light Company . . Beaver Valley 1 PWR 1601 13 13 0 I
Florida Power Corporation . Crystal River 3 PWR 1701 5 5 0 GPU Nuclear Corporation Three Mile Island 1 PWR 1901 23 23 0 Houston Lighting and Power Company South Texas 1 PWR 2201 7 7 0 Maine Yankee Atomic Power Company Maine Yankee PWR 2801 18 18 0 New York Power Authority Indian Point 3 PWR 3902 2 2 0 PECO Energy Company . Limerick i BWR 3701 '504 306 198 Public Service Electric and Gas Company Salem 1 PWR 4202 23 23 0 Salem 2 PWR 4203 34 35 -1 Tennessee Valley Authorjty . . Browns Ferry 2 BWR 4803 80 80 0 s
Toledo Edison Company . Davis-Besse PWR 5001 2 6 -4 Union Electric Company Callaway PWR 5101 2 2 0 Virginia Power . North Anna 1 PWR 5201 19 25 -6 Surry 1 PWR 5203 10 6 4
! i Wisconsin Public Service '
Corporation . Kewaunee PWR 5501 4 4 0 Total . .. .... . .. .... 798 610 188
'A total of 560 temporarity discharged assemblies were shipped from Long Island Power Authority's Shoreham plant to Limerick 1. Of these, a total of 56 temporanty discharged assemblies were reinserted in core at Limerick 1. See Technical Note 14 in Appendix E.
PWR = Pressurized-water reactor; BWR = Boiling-water reactor.
Note: Changes in number of temporarily discharged assemblies are due to discharge of additional temporarily discharged assemblies, reinsertion of previously discharged assemblies, and/or change in status of previously discharged assemblies.
Source-Energy information Administration. Form RW-859. " Nuclear Fuel Data"(1994).
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Arkansas Power and Light Company The ISFSI required the preparation of a 10 CFR 72 License Application, Safety Analysis Report, Environmental Report, and a Security Plan far NRC review and approval. The ,
in 1994, the Arkansas Power and Light Company's Arkansas license material was prepared and submitted to the NRC in {
Nuclear 1 & 2 plants finalized a contractual agreement with December 1989. Constmetion of the ISFSI west of the plant Sierra Nuclear for 14 VSC-24 casks that can hold up to 24 began in April 1991 after NRC approved the Environmental PWR assemblies. Report. He facility and its pre-operational testing were i completed in October 1992. ne ISFSI was licensed by the f Construbiorfof the concrete casks began in October 1994.
NRC on November 25,1992. j De cask storage will be on a concrete pad located within the existing security protected area at the Arkansas Nuclear plants.
The license allows Baltimore Gas cnd Electric Company to j ne pad is designed to hold 26 casks, but can be expanded to Pl ace as many as 2,880 assemblies in casks to be placed in j provide space for an additional 50' casks. Existing rail lines ISFSI's. Each NUHOMS cask at Calvert Cliffs can hold 24 and a new rail car specifically designed for the VSC will assembbes, ar.d there are currently 120 planned storage l transport the casks from the plant's Auxiliary Building to the m dules. On November 30,1993, the dry storage facility i storage pad.
became fully operational with the successful loading of the first cask of fuel. As of September 1995, a total of 240 assemblies were stored in 10 modules.
Baltimore Gas and Electric Company 1 1
The ISFSI at Baltimore Gas and Electric Company's Calvert Carolina Power and Light Company J Cliffs station is the NUllOMS-24P. The Calvert Cliffs ISFSI l
has bee 3 designed as a life-of-plant storage facility. The he ISFSI for Carolina Power and Light Company's Robinson j ISFSI will have the capacity to store all spent fuel discharged 2 plant is composed of 8 NUHOMS-7P horizontal storage j from Calvert Cliffs 1 & 2, beyond the spent fuel pool capacity, m dules (HSM's). Each HSM is a steel-re,mforced concrete ;
up to the 40-year plant life, if necessary, ne exact capacity j stmeture which holds 7 intact assembhes m each module. He needed is uncertain, and to limit capital investment until ISFSI ivas licensed by the NRC in August 1986 to hold 56 necessary, the ISFS! will be constructed in up to five phases. l u raarno infnemation Artminie,tration i Soent Nuclear Fuel Discharues from Ll.S. Reactots 1994
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DOCXEIED UNITED STATES OF AMERICA USHRC NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD W APR -7 P3 :26 In the Matter of )
ort
) p.
- CAROLINA POWER & LIGHT ) Docket No. 50-400 -OLA AD$u- .;p (Shearon Harris Nuclear ) ASLBP No. 99-762-02-LA Power Plant) )
)
CERTIFICATE OF SERVICE I certify that on April 5,1999, copies of the foregoing Orange County's Supplemental Petition to Intervene were served on the following by e-mail and/or first class mail as indicated below:
Secretary of the Commission Steven Carr, Esq.
Attention: Rulemakings and Adjudicions Carolina Power & Light Co.
Staff 411 Fayetteville Street Mall U.S. Nuclear Regulatory Commission Post Office Box 1551 - CPB 13A2 Washington, D.C. 20555 Raleigh, NC 27602-1551 E-mail: hearingdocket@nrc. gov E-mail: steven.carr@cpic.com Marian L. Zobler, Esq. Alice Gordon, Chair Office of the General Counsel Orange County Board of Commissioners U.S. Nuclear Regulatory Commission P.O. Box 8181 Washington, D.C. 20555 Hillsborough,NC 27278 E-mail: mlz@nrc. gov E-mail: gordonam@mindspring.com PaulThames Adjudicatory File County Engineer Atomic Safety and Licensing Board Orange County Board of Commissioners U.S. Nuclear Regulatory Commission P.O. Box 8181 Washington, D.C. 20555-0001 Hillsborough,NC 27278 Dr. Peter S. Lam Frederick J. Shon Atomic Safety and Licensing Board Atomic Safety and Licensing Board Mail Stop T 3F-23 Mail Stop T 3F-23 U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Com. mission Washington, D.C. 20555 Washington, D.C. 20555 E-mail: psl@nrc. gov E-mail: fjs@nrc. gov l
I
' John H. O'Neill, Jr., Esq. G. Paul Bollwerk, III, Chainnan William R. Hollaway, Esq. Atomic Safety and Licensing Board Shaw, Pittman, Potts & Trowbridge Mail Stop T 3F-23 2300 N Street N.W. U.S. Nuclear Regulatory Commission Washington, D.C. 20037-1128 Washington, D.C. 20555 E-mail: john _o'neill@shawpittman.com, E-mail: gpb@nrc. gov william.hollaway@shawpittman.com
,q l Diane Curran l
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