ML20235Z390
| ML20235Z390 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/07/1989 |
| From: | Mcneil S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235Z380 | List: |
| References | |
| NUDOCS 8903150413 | |
| Download: ML20235Z390 (2) | |
Text
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s 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318 NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Comission (Comission) has issued Amendment Nos.136 and 117 to Facility Operating License Nos. DPR-53 and DPR-69, respectively, to the Baltimore Gas and Electric Company which revised the Technical Specifications (TS) for operation of the Calvert Cliffs Nuclear-Power Plant, Unit Nos. I and 2 located in Calvert County, Maryland.
The amendments are effective as of the date of issuance.
The amendments modified TS 5.6.1, " Criticality - Spent Fuel," by increasing the U-235 enrichment limit for unf rradiated fuel stored in the spent fuel storage racks from 4.1 to 5.0 weight percent.
The application for the amendments complies with the standards and 1
. requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's tules and regulations. The Comission has made appropriate i
findings as required by the Act und the Commission's rules and regulations in A/
l 10 CFp ChapterfI, which are set forth in the license amendments.
Notice of Consideration of Issuance of Amendment ard Opportunity for Hearing in connection with this action was published in the FEDERAL REGISTER l
ort August 8, 1988 (53 FR 29791). No request for a hearing or petition for j
leave to intervene was filed following this notice.
8903150413 890307 l
PDR ADOCK 05000317 P
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. L The Commission has prepared an Environmental Assessment related to the action and has detennined not to prepare an environmental impact statement.
Based upon the environmental assessment, the Commission has concluded that the issuance of this amendment will not have a significant effect on the quality of the human environment.
For further details with respect to the action see (1) the application for amendment dated June 9, 1988, as supplemented on October 25, November 17.-
and December 28,1988,(2) Amendment Nos.136 and 117 to License Nos. DPR.53 and DPR_69, respectively, and (3) the Commission's related Safety Evaluation and Environmental Assessment. All of these items are available for public inspection at the Comission's Public Document Room, 2120 L Street, N. W.,
and at the Calvert County Library, Prince Frederick, Maryland. A copy of items (2) and (3) may be obtained upon requested addressed to the U. S.
Nuclear Regulatory Commission, Washington D. C. 20555 Attention:
- Director, Division of Reactor Projects I/II.
Dated at Rockville, Maryland, this 7th day of March 1989.
FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGNED BY Scott Alexander McNeil, Project Manager Division of Reactor Projects I/II i
Office of Nuclear Reactor Regulation
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- 03/ 2 /89
- 03/1 /89
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OFFICIAL RECORD COPY
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March 7,1989 1
Docket Nos. 50-317 DISTRIBUTION and 50-318 Docket F T NRC & Local PDRs PDI-1 RF GClainas BABoger CVogan Mr. G. C. Creel SAMcNeil OGC Vice President - Nuclear Energy DHagan EJordan Baltimore Gas and Electric Company BGr.imes TMeek (8 )
Calvert Cliffs Nuclear Power Plant
- Wanda Jones EButcher MD Rtes. 2 & 4 MWHodges ACRS (10)
P. O. Box 1535 GPA/PA ARM /LFMB Lusby, Maryland 20657 LTripp, RI
Dear Mr. Creel:
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SUBJECT:
AMENDMENT TO INCREASE ENRICHMENT LIMITS FOR THE SPENT FUEL STORAGE RACKS (TACS NOS. 68416 AND 68417)
The Comission has issued the enclosed Amendment No.136 to Facility Operating License No. DPR-53 and Amendment No.117 to Facility Operating License No.
DPR-69 for the Calvert Cliffs Power Plant, Unit Nos. I and 2', respectively.
The amendments consist of changes'to the Technical Specifications (TS) in response to your application transmitted by letter dated June 9, 1988 as supplemented on October 25, November 17 and December 28, 1988.
These amendments modified TS 5.6.1, " Criticality - Spent Fuel," by increasing the U-235 enrichment limit for unirradiated fuel' stored in the spent fuel storage racks from 4.1 to 5.0 weight percent U-235.
The NRC staff has determined that an increase in this enrichment limit to 5.0 weight percent U-235 for irradiated fuel stored in the spent fuel storage racks is acceptable contingent upon the acceptability of the NRC analysis for the generic fuel handling accident. This analysis is currently being finalized to generically support facility operations with enrichments of 5.0 weight percent U-235 and burnup levels of 60,000 MWD /MT and is expected to be available to support (1) your Unit 2 Cycle 9 reload amendment request, dated February 7,1989, and (2) approval of 5.0 weight percent U-235 enriched irradiated fuel assemblies in the Calvert Cliffs Units 1 and 2 spent fuel storage racks prior to the Unit 2 startup following the Cycle 9 refueling outage.
A copy of the related Safety Evaluation and the Notice of Issuance are enclosed.
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-2 March 7, 1989 K ;*
A copy of the Environmental Assessment related to this action was transmitted to you by letter dated January 25, 1989.
1 Sincerely ~
ORIGINAL SIGNED BY Scott Alexander McNeil. Project Manager Project Directorate I-1 Division of Reactor Projects, I/II
Enclosures:
1.
Amendment No.136:to DPR-53 2.
Amendment No.117 to DPR-69 3.
Safety Evaluation 4.
Notice 1
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See next page 1
[TACS68416/17]
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NAME :CVogan 1:ah _:RACapra
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- 03/nT89 DATE :03/ /89
- 03/d~/89' OFFICIAL RECORD COPY 1
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!j Mr. G. C. CreeF j
Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant i
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cc:
Mr. William T. Bowen, President Calvert County Board of Commissioners Prince Frederick, Maryland 20768 D. A. Brune, Esq.
General Counsel Baltimore Gas and Electric Company P. O. Box 1475 l
Baltimore, Maryland 21203 Mr. Jay E. Silberg, Esq Shaw, Pittman, Potts and Trowbridge 1800 M Street, NW Washington, DC 20036 Mr. W. J. Lippold, General Supervisor Technical Services Engineering Calvert Cliffs Nuclear Power Plant MD Rts 2 & 4. P. O. Box 1535 Lusby, Maryland 20657 Resident Inspector c/o U.S. Nuclear Regulatory Commission j
P. O. Box 437 l
Lusby, Maryland 20657 l
l Department of Natural Resources l
Energy Administration, Power Plant Siting Program ATTN: Mr. T. Magette
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Tawes State Office Building j
Annapolis, Maryland 21204 Regional strator, Region I U.S. Nucl latory Commission I
475 Allend619 d
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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE t
Amendment No.136 License No. OPR-53 1.
The Nuclear Re'gulatory-Commission.(the Commission) has,found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated June 9, 1988 as supplemented on October 25 November 17, and December 28, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the
)
and the Commission's rules and regulations set forth in 10 CFR Chapter I; 3
B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and securitytor to the hsalth and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comeission's regulations and all applicable requirements been.sattsfied.
2.
Ac
.,the license is amended by changes to the Technical 5
as indicated in the attachment to this license and paragraph 2.C.(2) of Facility Operating License No. DPR-53 is hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.136, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance. ~
FOR THE NUCLEAR REGULATORY Com ISSION lh 0.. CW Robert A. Capra, Director Project Directorate I -
Division of Reactor Projects. I/II
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Attachment:
Changes to the Technical Specifications Date of Issuance:
March 7, 1989
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UNITED STATES
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. A-BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO, 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 117 License No. DPR-69 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated June 9, 1988 as supplemented on October 25...
November 17, and December 28, 1988, complies with the standards and I
requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the app 1feation, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations _;
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and u,
E.
The issuance of this amendment is in accordance with 10 CFR Part the Camr.ission's regulations and all applicable requirements satisfied.
2.
the license is amended by changes to the Technical 5
as indicated in the attachment to this license a
'and paragraph 2.C.2 of Facility Operating License No.
)
DPR-69 is hereby amended to read as follows:
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The Technical Specifications contained in Appendices i
A and B, as revised through Aetndnent. No.117, art l
hereby incorporated in the license. The licensee shall J
operate the facility in accordance with the Technical i
Specifications.
This license amendment is effective as of Ue}date of its issuance.
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FOR THE NUCLEAR REGULATORY COMISSION 5 & 0. YW j
Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects, I/II 3
Attachment:
I Changes to the Technical Specifications 1
Date of Issuance: March 7, 1989
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ATTAC N NT TO LICENSE AMENOMENTS
_nv NO. 136 FACILITY OPERATING LICENSE NO. DPR-53 l
l AMENDNENT NO. 117 FACILITY OPERATING LICENSE NO. DPR-69 l
DOCKET NOS. 50-317 AND 50-318 Revise Appendix A as follows:
Remove Pages Insert Pages 5-5 5-5 5-6*
5-6*
- 0verleaf provided for continuity purposes.
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DESIM FEATURES M
5.4.2 The total water and steam volume of the reactor coolant system is 10.814
- f. 460 cubic feet at a nominal T,,, of $32*F',
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 Yhe meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY - SPENT FUEL 5.6.1 The spent fuel storage racks are designed and shall be maintained with a minimum 10 3/32" x 10 3/32" center-to-center distance between fuel assemblies placed in the storage racks to ensure a k storage pool filled with unborated water.,ff equivalent to < 0.95 with the The k of < 0 95 includes the conservative allowances for uncertainties describNfin Sktion 9.7.2 of the FSAR. The maximum fuel enrichment to be stored in the fuel pool will be 4.1 weight percent for irradiated fuel
- and 5.0 weight percent f o r f wel that has not been irradiated.
CRITICALITY - NEW FUEL
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5.6.2 The new fuel storage racks are designed and shall be maintained l
with a nominal 18 inch center-to center distance between new fuel assemblies i
such that k p will not exceed 0.95 when fuel having a maximum enrichment of l
5.0 weight ecent U-235 is in place and various densities of unborated water i
are assumed including aqueous foam moderation and full flood conditions. The klfr of 10.95 includes the conservative allowance for uncertainties describ 1 Section 9.7.2 of the FSAR.
DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 63 feet.
i CAPACITY 5.6.4 The fuel storage pool is designed and shall be maintained with a combined storage capacity, for both Units 1 and 2.11mited to no more than 1830 fuel assemblies.
i 5.7 COMP 0NENT CYCLIC OR TRAN51ENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within.'the cyclic or transient ' Aits of Tab.le 5.7-1.
- Irradiated fuel is fuel that has experienced the critical state (K,gg greater than or equal to one).
CALVERT CLIFFS - UNIT 1 5-5 Amendment No.gy, (7, g), 69, 46/. 1:
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.E E 5.4.2 The total water and steam volume of the reactor coolant system is 10.614 l
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5.5 MET'c0ROLOGICAL TOWER t.0 CATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE i
l CRITICALITY - SPENT FUEL l
5.6.1 The spent fuel storage racks are designed and shall be maintained with a minimum 10 3/32" x 10 3/32" center-to-center distance between fuel assemblies placed in the storage racks to ensure a k,ff equivalent to < 0.95 with the storage pool filled with unborated water.
The k of < 0795 includes the conservative allowances for uncertainties describNfin Section 9.7.2 of the FSAR. The maximum fuel enrichment to be stored in the fuel pool will be 4.1 weight percent f or irradiated fuel
- and 5.0 weight percent for fu.a1 that has not been irradiated.
CRITICALITY - NEW FUEL I
5.6.2 The new fuel storage racks are designed and shall be maintained with a nominal 18 inch center-to center distance between new fuel assemblies 5.0 weight gf will not exceed 0.95 when fuel having a maximum enrichmen such that k are assumed including aqueous foes moderation and full flood conditions. The fr f i 0.95 includes the conservative allowance for uncertainties described k
o ilsection9.7.2oftheFSAR.
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DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 63 feet.
CAPACITY 5.G.4 The fuel storage pool is designed and shall be maintained with a combined storage capacity. for both Units 1 and 2. limited to no more than 1830 fuel assemblies.
5.7 C(Mp0NENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within 'the cyclic or transient limits of Table 5.7-1.
- Irradiated fuel is fuel that has experienced the critical state (K,gg greater than or equal to one).
CALVERT CLIFFS - UNIT 2 5-5 Amendment No. 12. 79. ff. R. A 117
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EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
TO FACILITY OPERATING LICENSE N0. DPR-53 AND AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO DPR-69 BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR p0WER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-317 AND 50-318 U-235 ENRICHMENT INCREASE FOR THE SPENT FUEL P0OL i
1.0 INTRODUCTION
i l
By its letter dated June 9, 1988, Baltimore Gas and Electric Company (864
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the licensee) requested that the Calvert Cliffs Units 1 and 2 Technicale 4
Specifications (TS) 5.6.1, " Criticality - Spent Fuel," be modified by increasing the enrichment limit for fuel which may be stored in the spent fuel storage racks from 4.1 to 5.0 weight percent U-235.
2.0 EVALUATION The Calvert Cliffs spent fuel storage racks consist of square stainless steel cells having an inside dimension of 8-9/16 inches. The inner wall of each storage cell is made of a 0.060 inch thick sheet of 304L stainless steel. A Boraflex sheet 6-1/2 inches wide is sandwiched between this inner wallandanexternal0.060inchthickstainlesssteelgheet.i ) loading of 0.020 The Boraflex sheet 1s 0.90 inches thick with a nominal boron-10 (B 2
ge/cm. The average distance between the centers of these cells is 10.09 inches. Spent fuel is nomally stored in pool water containing about 2300 ppm of soluble boron. This normal storage arrangement would result in ext (configurations. However, for conservatism, the spent fuel lated assuming no soluble boron in the water.
1theeffectivemultipitcat18n)transporttheorycode 1 discrete ordinates (S The factor (k Neutron cross section data b) of the was spentt
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ENDF/8-If rary was generated for input to this code using the CEPAK code. This model has been benchmarked against experimental data and has been found to adequately reproduce the critical values.
The spent fuel pool criticality calculations were also based on no burnsole poison or control rods in the fuel assemblies, unirradisted fuel with 5.0 weight percent U-235, and, as previously mentioned, no soluble boron in the water.
In addition, the most adverse effects of temperature, eccentric
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. i placement of fuel assemblies and poison boxes, changes in steel thickness, change in center to center spacing, boron poison loss possible over the life of the Boraflex, and the calculational uncertainty were included in the following manner. The squares of each delta-k change were added and the square root of the sum was taken. This result was then added to the calculational bias of -0.00138 and the nominal K of 0.93678 giving a K
of0.946includingalluncertaintiesata98N5 probability / confidence 18N1.
This meets the NRC limiting acceptance criterion of k Consequently, the NRC staff concludes that the spin no greater than 0.95.
fuel storage' racks at Calvert Cliffs Units 1 and 2 can accommodate, with respect to i
criticality, fuel having a maximum enrichment of 5.0 eight percent U-235.
1 Recently the NRC staff has expressed concerns regarding the possibility of gaps developing in Boraflex sheets due to irradiation induced axial shrinkage. This concern was documented in NRC Information Notice No. 87-43.
In response, the licensee has performed an analysis to determine the reactivity effects of Boraflex gap formation in the Calvert Cliffs spent fuel pool. The results indicate that, even with the assumption of a J
complete loss of soluble boron in the pool water, sufficient margin is s
available to acconnodate nearly a 4 inch vertical gap in every Boraflex sheet at the active fuel centerline without exceeding the NRC limiting criterion of a maximum k of 0.95.
Although the licensee has no surveillance requirements fn place for detecting degradation of the full f
length Boraflex sheets, it has a poison coupon monitoring program to detect degraded Boraflex specimens which would indicate any extreme shrinkage or loss of neutron absorption properties.
In addition, since the installation process for the Boraflex assemblies involved only single sheets, that are not fastened or permanently glued onto any surface or structure, gap formation due to Boraflex shrinkage would not be expected. Based on the above and on nonnal spent fuel pool conditions, that it contains sufficient soluble boron to more than offset any reactivity increase due to Boraflex degradation, the NRC staff finds the use of Boraflex in the Calvert Cliffs spent fuel pool design to be an acceptable means of meeting the required I
acceptance criteria.
In the Dec
- 28, 1988 letter, BG8E committed to considering the fuel handling accident i Unit 1 or 2 core reload analysis to ensure that the accident analysis all possible U-235 enrichment and fuel burnup levels for each spec 1 assembly in the reactor core or the spent fuel pool. The NRC staff fi analytical approach to be acceptable.
I HoweveN until final completion of the NRC generic fuel handling accident analys w for 5.0 weight percent U-235 enriched fuel with burnup levels up to 60,000 MWD /MT, TS 5.6.1, " Criticality - Spent Fuel," cannot be modified to permit the storage of irradiated fud with U-235 enrichment levels above that currently permitted at Calvert Cliffs, specifically 4.1 weight percent U-235 l
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Consequenti the NRC staff has determined that an increase in the enrichment limit of TS 5.6.1 for unirradiated fuel stored in the spent fuel storage racks, to a value up to and including 5.0 weight percent U-235 is acceptable. Furthermore, the staff has determined that an increase in' the TS 5.6.1 enrichment limit up to and including 5.0 weight percent U-235 for irradiated fuel is acceptable, contingent upon the acceptability of the NRC generic fuel handling accident analysis, but that the TS 5.6.1 enrichment limit shall not be modified for irradiated fuel until this contingency is satisfied.
l 3.0 INTENT The intent of the proposed change is to pemit the storage of fuel, that is not irradiated, with enrichment levels up to and including 5.0 weight percent U-235, in the spent fuel storage racks.
Irradiated fuel is fuel that has experienced criticality (i.e., keff greater than or equal to 1.01.
4.0 STATE CONSULTATION
S A Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Prior Hearing was published in the Federal Register on August 8, 1988 (53 FR 28791). No hearing requests or intervention petitions were received. The State of Maryland was consulted on this matter and had no comments on the determination.
5.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR 51.21, 51.32 and 51.35, an environmental assessment and finding of no significant impact was published in the Federal Register on January 30, 1989 (53 FR 435?).
Accordingly, based upon the environmental assessment, the Comission has detemined that issuance of this amendment will not have a significant effect on the quali,
...ef the human environment.
6.0 C We have lased on the considerations discussed above, that:
(1) there is rea rance that the health and safety of the public will not be endangered operation in the proposed manner, and (2) such activities will i
be conducted in compliance with the Comission's regulations and (3) the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
PRINCIPAL CONTRIBUTORS:
L. Kopp, S. McNeil Dated: March 7, 1989
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UNITED STATES NUCLEAR REGULATORY COMMISSION BALTIMORE GAS AND ELECTHIC COMPANY CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318 NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Comission (Comission) has issued
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Amendment Nos.136 and 117 to Facility Operating License Nos. DPR-53 and DPR-69, respectively, to the Baltimore Gas and Electric Company which revised the Technical Specifications (TS) for operation of the Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 located in Calvert County, Maryland.
The amendments are effective as of the date of issuance.
I The amendments modified TS 5.6.1, " Criticality - Spent Fuel," by increasing the U-235 enrichment limit for unirradiated fuel stored in the spent fuel storage racks from 4.1 to 5.0 weight percent.
The application for the amendments complies with the standards and
. requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations. The Comission has made appropriate findings a ired by the Act and the Comission's rules and regulations in 10 CFR C I, which are set forth in the license amendments.
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Notice of Consideration of Issuance of Amendment and Opportunity for Hearing in connection with this action was published in the FEDERAL REGISTER on August 8, 1988 (53 FR 29791). No request for a hearing or petition for j
leave to intervene was filed following.this notice.
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,L, The Caumidion has prepared an Environmental Assessment related to the action and has determined not to prepare an environmental impact statement.
3 Based upon the environmental assessment, the Commission has concluded that t
i the issuance of this amendment will not have a significant effect on the quality of the human environment.
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For further details with respect to the action see (1) the application for amendment dated June 9, 1988, as supplemented on October 25, November 17, and December 28, 1988 (2) Amendment Nos.136 and 117 to License Nos. DPR_53 and DPR-69, respectively, and (3) the Comission's related Safety Evaluation and Environmental Assessment. All of these items are available for public inspection at the Commission's Public Document Room, 2120 L Street, N. W... f and at the Calvert Cot;nty Library, Prince Frederick, Maryland. A copy of items (2) and (3) may be obtained upon requested addressed to the U. S.
Nuclear Regulatory Comission, Washington D. C. 20555, Attention: Director, Division of Reactor Projects I/II.
Dated at Rockville, Maryland, this 7th day of March 1989.
FOR THE NUCLEAR REGULATORY COP 9 FISSION i
l ORIGINAL SIGNED BY l
Scott Alexander McNeil, Project Manager W.4 Division of Reactor Projects I/II p'A Office of Nuclear Reactor Regulati n q) h 5
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- RACapra NAME :CVogan DATE 103/'o/89
- 03/2/89
- 03/1 /89
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