ML20203B434
| ML20203B434 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/02/1986 |
| From: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| To: | Thadani A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20203B439 | List: |
| References | |
| NUDOCS 8607180211 | |
| Download: ML20203B434 (4) | |
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BALTIMORE GAS AND ELECTRIC CHARLES CENTER R O. BOX 1475 BALTIMORE, MARYLAND 21203
. Joseph A.TIERNAN Vict PRESIDENT NucLLAn ENERGf July 2.1986 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 ATTENTION:
Mr. A. C. Thadani, Project Director PWR Project Directorate #8 Division of PWR Licensing - B
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Updated Final Safety Analysis Report
REFERENCE:
10 CFR 50.71, " Maintenance of Records, Making of Reports" Gentlemen:
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The Baltimore Gas and Electric Company forwards herewith, for your information and use, one signed original and twelve additional copies of Revision 5 to the Updated Final Safety Analysis Report (FSAR) for the Calvert Cliffs Nuclear Power Plant Unit Nos.1 &
2.
These copies are provided in accordance with 10 CFR 50.71(e), which requires that power reactor licensees periodically update the FSAR that was submitted with the operating license application. The enclosed revision is the product of an ongoing effort at Baltimore Gas and Electric Company to ensure that the FSAR accurately reflects current plant design 1 formation.
Attachment I to this letter identifies facility changes made under the provisions of 10 CFR 50.59 and reflected in this revision, but not previously reported to the Commission. The List of Effective Pages for the FSAR is included with the enclosed revision.
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8607180211 860702 ~
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PDH ADOCK 0D000317
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Mr. A. C. Thadani July 2,1986 Please replace the appropriate pages of your copy (s) of the updated FSAR with the enclosed pages. Then please complete and return the Transmittal of Document form included as Attachment 2 to this letter.
Very truly yours.
/w W STATE OF MARYLAND:
TO WIT:
CITY OF BALTIMORE :
1 Joseph A. Tiernan, being duly sworn states that he is Vice President of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregoing response for the purposes therein r:t forth; that the statements made are true and correct to the best of his knowledge, information, and belief; and that he was i
authorized to provide the response on behalf cf said Corporation.
WITNESS my Hand and Notarial Scal:
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Notary 1%blic My Commission Expires:
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61' Attachments Enclosures D. A. Brune, Esquire (w/o enclosures) cc:
- 3. E. Silberg, Esquire (w/o enclosures)
D. H. Jaffe, NRC (w/o enclosures)
T. Foley, NRC (w/o enclosures)
3-July 2,1986 Mr. A, C.' Thadani 1
bcc:
R. F. Ash /R. C. L. Olson C. H. Cruse /P. E. Katz
- R. E. Denton/3. A. Mihalcik
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R. M. Douglass/T. N. Pritchett M. Gavrilas/E I. Bauereis
- 3. R. Lemons /R. P. Heibel W. 3. Lippold/A. R. Thornton F. 3. Munno R. B. Pond, Jr./R. E. Cantrell L. B. Russell /3. T. Carroll V. F. Stricklin (3)
W. P. McCaughey, Jr.
W. R. Horlacher, Ill B. E. Holian P. E. McGrane M. E. Bowman L. E. Salyards A. E. Edwards B. 3. Pasko M. 3. Warren k
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. Mr. A. C. Thadani Attachm2nt 1 July 2,1986
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List of Facility Change Requests reflected in Revision 5 of the Updated FSAR and not
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. yet reported in an Annual Report per Paragraph 50.59(b).
79-1062 82-43 83-103 83-145 83-3001 84-5?
84 84-93 84 84-96 84-1077 85-17 85-80 85-1054 85-3001, Supp. I t 2 86-12 86-13 86-35 4
86-36 l
86-48 86-49 86-50 I
86-59 86-300l*
FCR 86-3001 documents a new analysis.of the Steam Generator Tube Rupture Accident described in Section 14.15 of the FSAR. In order to ensure plant operating conditions are bounded, this analysis deletes credit for turbine bypass valve operation
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prior to initiation of cooldown. The calculated site boundary thyroid dose is 1.0 REM vs.
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0.34 REM previously reported. Mr. Jaffe of the NRC staff was informed of these results and of our plans to include the new analysis in this FSAR revision. The revised FSAR Steam Generator Tube Rupture analysis does not pose any significant hazards
. considerations because it does not:
- 1. Involve a significant increase in the probability or consequence of an accident previously evaluated. The probability of the Steam Generator Tube Rupture is unchanged, since there are no changes to plant hardware or procedures assumed by this analysis. The calculated site boundary thyroid dose of 1.0 REM is a very small fraction of the 10 CFR 100 limit of 300 REM.
- 2. Create the possibility of a new or different kind of accident from any accident previously evaluated. The change to the FSAR 14.15 analysis does not affect plant hardware, or operating and maintenance practices.
No new accident scenario is created.
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- 3. Involve a significant reduction in a margin of safety. Calculated site boundary thyroid doses remain a small fraction of 10 CFR 100 limits.
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