ML20052F724
| ML20052F724 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/04/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052F725 | List: |
| References | |
| NUDOCS 8205130504 | |
| Download: ML20052F724 (10) | |
Text
_ _ _ _ _ _ _ _ _ _ - - - _ _ _
jp teg'o
/
UNITED STATES
'g
[S g
NUCLEAR REGULATORY COMMISSION g
wAssiworow. o. c. 20sss Y
p BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Conpany (the licensee) dated October 30, 1981, complies with the standards and 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 conformity 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 security or to the health and safety of the public; and
~
E.
The issuance of this amendment is in accordance with l'0 CF'R Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
ep a
G 8205130504 020504 PDR ADOCK 05000317 P
. 2.
Accordingly, the license is amended by changes to the Technical Specifications 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:
(2) Technicil Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 69, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendmen't is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
>$u$
'^'
bobert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 4, 1982
- e e
l O
l L
ATTACHMENT TO LICENSE AMENDMENT NO. 69 FACILITY OPERATING LICENSE N0. DPR-53 DOCKET NO. 50-317 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
Page 5-5 t
O G
ip a
a
,l a
~,, -, -,,-
r
DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 10,614
+ 460 cubic feet at a nominal T,yg of 532*F.
5.5 METEOROLOGICAL TOWER LOCA710N 5.5.1 The meteor'ological 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 equivalent to < 0.95 with the storage pool filled with unborated water.,ffThe k of < 0.95 includes the conservative allowances for uncertainties describ88 fin Section 9.7.2 of the FSAR. The maximum fuel enrichment to be stored in the fuel pool will be 4.1 weight percent.
CRITICALITY - NEW FUEL 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 such that k
will not exceed 0.98 whan fuel having a maximum enrichment of 4.1 weight pINent U-235 is in place and various densities of unborated water are assumed including aqueous foam moderation.
The k of < 0.98 includes the conserva-tiveallowanceforuncertaintiesdescribe8SnSection9.7.2oftheFSAR.
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 5.6.4 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.
l
^
5.7 COMPONENT 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.
l I
CALVERT CLIFFS - UNIT 1 5-5 Amendment No. 27, y, (;3, 69 i
k
l TABLE 5.7-1 9
COMPONENT CYCLIC OR TRANSIENT LIMITS M
- o
]
Compo'nent Cyclic or Transient Limit Design Cycle or Transient F.
]
Reactor Coolant System 500 heatup and cooldown cycles 70*F to 532*F to 70*F v,
g 400 reactor trip cycles 100% to 0% RATED THERMAL POWER Z
10 Primary Hydrostatic Tests 3125 psia and 60*F > NDTT 320 P'rimary Leak Tests 2500 psia and 60*F > NDTT 9'
Steam Generator 10 Secondary Hydrostatic Tests 1250 psia Secondary Side and temperature > 100*F 320 Secondary Leak Tests s
1000 psia Secondary Side With Primary - Secondary ap of 820 psi and shell side temperature between 100*F and 200*F e
e
g,4
'*,g, UNITED STATES NUCLEAR REGULATORY COMMISSION f
- l WASHINGTON, D. C. 20555
%, *... + sd BALTIMORE GAS AND ELECTRIC COMPANY DOCKET N0. 50-318
.CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. DPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Corpany (the licensee) dated October 30, 1981, complies with the standards and 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 aperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) 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 o
E.
The issuance of this amendment is in accordance with 10 CFR
~
Part 51 of the Commission's regulations and all applic'able'~
requirements have been satisfied.
e
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating Licens.e No. DPR-69 is hereby amended to read as follows:
2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 52, 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 COMMISSION.
- u 3
A l
-y f
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing l-
Attachment:
Changes to the Technical Specifications Date of Issuance: May 4, 1982
\\
s em l
f O
g b
(
+
e
i ATTACHMENT TO LICENSE AMENDMENT NO. 52 FACILITY OPERATING LICENSE N0. DPR-69 DOCKET NO. 50-318
. Replace the following'page of the Appendix A Technical Specifications with the enclosed page as indicated.
The revised page is identified by Ainendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
l i
Page 5-5 1
g 4 m g w
3 e
DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 10,614
+ 460 cubic feet at a nominal T,yg of 532*F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The 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 equivalent to < 0.95 with the storage pool filled with unborated water.effThe k of < 0.95 includes the conservative allowances for uncertainties describ8 bin Section 9.7.2 of the FSAR. The maximum fuel enrichment to be stored in the fuel pool will be 4'.1 weight percent.
CRITICALITY - NEW FUEL 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 such that k
will not exceed 0.98 when fuel having a maximum enrichment of 4.1 weight p$((ent U-235 is in place and various densities of unborated water are assumed including aqueous foam moderation. The k of < 0.98 includes the conserva-tive allowance for uncertainties describe 89n 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.
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, limited to no more than 1830 fuel assemblies.
l 5.7 COMPONENT 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.
CALVERT CLIFFS - UNIT 2 5-5 Amendment No. J2, 30, //5, 52
l I
e TABLE 5 7-1 9
COMPONENT CYCLIC OR TRANSIENT LIMITS G
mx Component Cyclic or Transient Limit Design Cycle or Transient i
0; Reactor Coolant System 500 heatup and cooldown cycles 70*F to 532'F to 70*F G
g 400 reactor trip cycles 100% to 0% RATED THERMAL POWER
-4 10 Primary Hydrostatic Tests 3125 psia and 60 F > NDTT i
320 Primary Leak Tests 2500 psia and 60*F > NDTT p.
Steam Generator 10 Secondary Hydrostatic Tests 1250 psia Secondary Side and temperature > 100 F 320 Secondary Leak Tests 1000 psia Secondary Side With Primary - Secondary Ap of 820 psi and shell side p
temperature between 100*F o
and 200*F 5.
2 a
F I
g e
e 1
t l
e I