ML20044B133
| ML20044B133 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/06/1990 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044B134 | List: |
| References | |
| NUDOCS 9007170384 | |
| Download: ML20044B133 (7) | |
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UNITED STATES 2
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.g NUCLEAR REGULATORY COMMISSION
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BALTIMORE. GAS.AND ELECTRIC; COMPANY 00CKET.NO. 50-317 CALVERT. CLIFFS. NUCLEAR. POWER PLANT,. UNIT-1 AMENDMENT.TO. FACILITY.0PERATING. LICENSE Amendment No.
License No. Dt
- 1.,
The Nuclear Regulatory Comission (the Commission) has found that-A.
The application for amendment by Baltimore Gas and Electric Compan;-
-(thelicensee)datedApril-30,1990, complies with the standards ar requirements of the Atomic' Energy Act of 1954, as amended (the Act) and the~Comission's rules and regulations set forth in 10 CFR Chapter I; B.
-The facility will operate in conformity with the application,
.the provisions of the Act, and the rules and regulations of the Commission; C.
Thereisreasonableassurance-(i)thattheactivitiesauthorized 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 E.
'The issuance of this amendment is in accordance with 10 CFR Part 51 of the.Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specif.ications as indicated in the attachment to this license-amendment, and paragraph 2.C.(2) of Facility Operating License
.No. DPR-53 is hereby amended to read as follows:
i 9007170384 900706 ADOCK0500gg7 DR
k-I (2) Technical. Specifications
~
The Technical Specifications contained in Appendices 1
A and B, as revised through Amendment No. 144, are l
hereby incorporated in the license. The l'.tnsee'shall 5
operate the facility in accordance with the rechnical Specifications, s,
n; e
3.
-This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
I FOR THE NUCLEAR REGULATORY COMMISSION
- Nb 2e Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Heactor Regulation
Attachment:
. Changes to the Te;nnical Specifications
.Date.of Issuance: July 6,1990
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fo, UNITED STATES '-
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g NUCLEAR REGULATORY COMMISSION
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w BALTIMORE GAS AND ELECTRIC COMPANY D0LKET.NO.' 50 318-CALVERT CLIFFS. NUCLEAR. POWER PLANT. UNIT.2
. AMENDMENT.TO. FACILITY'0PERATING-LICENSE Amendment No. 127-
' License No. DPR-69 1.
' The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (thelicensee)datedApril 30, 1990, complies with the standards and
. requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and _ regulations set forth in 10 CFR Chapter I;
(.
B..
The facility will operate in conformity with the application, i
the provisions of-the Act, and the rules and regulations of the Comission; C~
There is reasonable assurance -(i) that the activities authorized by this amendment can be conducted without endangering the,realth and safety of_the public, and (ii) that suc't activities will be i
conducted in. compliance with the Comission's regulations; i
D.
The issuance of this amendment will not be inimical to the comon-defense ar.d security or to.the health and-safety of the public; and L
E.
The issuance of this amendment is in accordance with 10 CFR Part-i 51 of the Comission's regulations and all applicable requirements have.been-satisfied.
2.
Accordingly, the license is amended.by changes to the Technical l
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No.
- DPR-69 1s bereby amended to read as follows:
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2 (2) Technical; Specifications The Technical Specifications contained in Appendices A-and B, as revised through Amendment No.127, 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 and shall be implemented within-30 days.
w FOR THE NUCLEAR REGULATORY COMMISSION mk hhw
[ Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 6, 1990 E
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ATTACHMENT.TO LICENSE AMENDMENTS AMENDMENT.NO.144 FACILITY OPERATING-LICENSE.NO. DPR-53
'AMENDNENT.NO.127.. FACILITY.0PERATING LICENSE.NO.-DPR-69 DOCKET NOS. 50-317.AND 50-318L Revise Appendix A as follows:
' Remove.Page Insert Page 3/4 9-16 3/4 9-16 k
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.i REFUELING OPERATIONS' SPENT FUEL CASK HANDLING CRANE LIMITING CONDITION FOR OPERATION 3.9.13-Crane travel of the spent fuel shipping cask crane shall be restricted to prohibit a spent fuel shipping cask from travel over any I
area within one shipping cask length of any fuel assembly.
APPLICABILITY: With fuel: assemblies in the storage pool.
. ACTION:
With-the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of-Specification 3.0.3 are not applicable.
SURVEllLANCE RE0VIREMENTS 4.9.13 Crane interlocks and physical stops which restrict a spent fuel shipping cask from passing over any area within one shipping cask length of any fuel assembly shall be demonstrated OPERABLE within 7 days prior-to crane use and at least once per 7 days thereafter during crane operation.
These. conditions are modified to permit shipping cask travel to and from the cask pit in the presence of fuel within one cask length radius of the pathway provided the boric acid concentration in the spent fuel pool is greater than or equal to 1000 ppm AND the following criteria are met-by all assemblies within one_ cask length radius of the pathway:
- 1) Initial enrichment less than or equal to 4.1 w/o U-235,
- 2) Burnup -
greater than or equal to 28,000 MWD /MTU, and 3) Greater than 440 days-elapsed frote the. shutdown of the last operating cycle in which the assembly was present in the core. Crane -interlocks and physical stops which restrict a spent fuel shipping cask from passing over any area within one shipping cask length of any fuel assembly not satisfying the above criteria shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to using the crane for moving a cask within one length of fuel assemblies a
meeting the above criteria. These modifications are applicable only to the shipment of fuel rods supporting the EPRI sponsored hot-cell work for the shipment of a reactor vessel weld material surveillance capsule.
CALVERT CLIFFS - UNIT 1 3/4 9-16 Amendment No. 144
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BEFUELING'0PERATIONS SPENT FUEL CASK HANDLING CRANE LIMITING CONDITION FOR OPERATION 3.9.13. Crane travel of the spent fuel shipping cask crane shall be restricted to prohibit a spent fuel shipping cask from travel'over any area within one shipping cask length of any fuel assembly.
l APPLICABILITY: With fuel assemblies in the storage pool.
ACTION:
r With the requirements of the above specification not satisfied, place the h
crane load in a safe condition.
The provisions of Specification 3.0.3 are not applicable.
t SURVEILLANCE RE0VIREMENTS i
4.9.13: Crane interlocks and physical stops which restrict a spent fuel shipping cask from passing over any area within one shipping cask length of any fuel assembly shall be demonstrated OPERABLE within 7 days prior to crane use and at least once per 7 days thereafter during crane operation.
l These conditions are modified to permit shipping cask travel to and from the cask. pit in the presence of fuel within one cask length radius of the pathway provided the boric acid concentration in the spent fuel pool is-greater than or equal to 1000 ppm AND the following criteria are met by-all assemblies within one cask' length radius of the pathway:
+
- 1) Initial enrichment less than or equal to 4.1 w/o U-235, 2)-Burnup greater than or equal to 28,000 MWD /MTU, and 3) Greater than 440 days elapsed from the shutdown of the last operating cycle in which the assembly was present in the core.
Crane interlocks.and physical stops which restrict a spent fuel shipping cask from passing over any area within one shipping cask length of any fuel assembly not satisfying the above criteria shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to using the crane for moving a cask within one length of fuel assemblies meeting the above criteria.
These modifications are applicable only to the shipment of fuel rods supporting the EPRI sponsored hot-cell work for
~
the shipment of a reactor vessel weld material surveillance capsule.
l l
CALVERT CLIFFS - UNIT 2 3/4 9-16 Amendment No.127
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