ML20115B275
| ML20115B275 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/02/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20115B258 | List: |
| References | |
| NUDOCS 9210150377 | |
| Download: ML20115B275 (3) | |
Text
I f%
/
j'\\
i;e UNITED STATES NUCLEAR REGULATORY COMMISSION
?
k h
[
WASHINGTON o C TJ!,%
4.'.v y
_SEETY EVALUATION Bf TH[_0[1]f_E_0F NUfLE AR RJACTOR R(CM AJ103 R[L A.T Ull0_jdMM[BT _ NO.175 1(L F ACll.lT Y OPLP A_T l NG L IC[AS[_fjQJ}1-M AND AM[ fide [NT NO.15? TO FKlit TY OPERATlNG LIRNSE N0dP_Pd2 P
BAlll!inRLOM AND_11[QRjf COMPANY C ALY[RT CLLFFS NUCLEAR POW [R PL ANT. UNIT fl05.1 AND_2 DOFV[T NOS. 50-1]7 AND 50-313 1.0 INTRODUCT10N By letter dated July 28, 1992, Baltimore Gas and Electric Company (the licensee) indicated that the planned upgrade of the spent fuel cask handling crane to a single-failure-proof design at the Calvert Cliffs facility would be delayed.
Amendment flo.166 to Facility Operating License flo. OPR-53 and Amendment No.146 to Facility Operating License No. CPR-69 for the Calvert Cliffs fluclear Power Plant, Units 1 and ?, respectively, were issued on January 17, 1992.
The amendments were effective as of the date of their issuance and were to be implemented when the spent fuel cask handling crane modifications were complete prior to July 31, 1992.
By letter dated August 13, 1992, the licensee requested that the implementation date be revised to no l eer than December 31, 1992.
2.0 FVALVATION The lechnical Specifications (TS) revisions issued by Amendments 166 and 146 were to support the planned upgrade of the spent fuel cask handling crane to a single-failure-proof design.
The crane will be upgraded to handle the new l
spent fuel transfer cask which will be used to transfer spent fuel to the new independent Spent fuel Storage Installation (ISFSI) which is currently being constructed on the plant site.
The ISFSI transfer cask will weigh 90 tons, when loaded with spent fuel, which is three times that previously analyzed for a cask load drop.
The curi:nt TS restrict the movement of heavy loads greater than 1600 pounds over fuel assemblies by the existing spent fuel cask handling crane.
l The licensee's August 13, 199c, letter indicated that the installation of the upgrades to the cask handling crane to a single-failure-proof design had been delayed due to changes in the Unit I refueling outage schedul and the identification of additional engineering design effort neces. y to support l
the installation of the upgrades to the crane.
9210150377 921002 PDR ADOCK 05000317 P
O
. As noted above, the current TS govern the use of the existing cask handling crane and restrict the movement of heavy loads greater than 1600 pounds over fuel assemblies.
Therefore, the request to revise the implementation date from no later than July 31, 1992, to no later than December 31, 1992, does not inpact the 15 restrictions on the existing crane, is consistent with the proposed design modifications, and is, therefore, acceptable.
3.O SLAlL_Q!!SMLT AT In!j in accordance with the Commission's regulations, the Maryland State official was notified of the proposed issuance of the amendments.
The State official had no comments.
4.O FNVILOMi[N1M CO![SJRRAT10))
The amendments change a requirement with respect to installation or use of a facility temponent located within the restricted area as defined in 10 CFR Part 20.
The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occup4tional radiation exposure.
The Commission had previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public conaent on such finding (57 FR 40208).
Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 01LCLU_S100 The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor-Daniel G. Mcdonald Date: October 2, 1992
I -
Docket llos. 50-317 Octs er 2, 1992 and 50-318 Mr. Robert E. Denton Vice President - fluclear Energy Baltimore Gas and Elect ric Company Calvert Cliffs fluclear Power Plant MD Rts. 2 & 4 P. O. Box 1535 Lusby, Maryland 20657
Dear Mr. Denton:
SUBJECT:
ISSVAf1CE Of AMLilDMEllTS FOR CALVERT Cliff S tlVCLEAR POWER PLAfil, Utill fl0.1 (TAC fl0. M84261) AllD VillT t10. 2 (TAC 110. MB4262)
The Commission has issued the enclosed AmerJment fio.175 to f acility Operatty License flo. DPR-53 and Amendment flo 152 to f acility Operating License flo.
DPR-69 for the Calvert Cliffs fluclear Power Plant, Unit llos. I and 2, respec-tively.
The amendments are in response to your application transmitted by letter dated August 13, 1992.
The amendments revise the implementation date for Amendment llos. 166 and 146 for Units 1 and 2, respectively, which were issued on January 17, 1992.
flo changes to the Technical Specification pages are involved.
The implementation date for Amendment flos.166 and 146 is revised to ro later than December 31, 1992.
A copy of the related Safety Evaluation is enclosed.
A flotice of issuance will be included in the Commission's next regular biweekly federal Reuister notice.
Sincerely, Original Signed By:
Daniel G. Mcdonald, Senior Project Manager Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of fluclear Reactor Regulation
Enclosures:
1.
Amendment No.175 to DPR-53 2.
Amendment No.152 to DPR-69 3.
Safety Evaluation cc w/ enclosures:
See next page PDl-1:PMkN,OGC PDI-1:D 0" K E PDl-1:LA WE CVogan ee DMcDonald: avl
' Ib RACapra M our i/d /92 cA A% /92
- /J2/92 jp /ol/92
/
/
OFFICIAL RECORD COPY flLEllAME; A:\\CCMS4261.AMD
\\
_ _ _ - _ _ _ _ _