ML20002A292
| ML20002A292 | |
| Person / Time | |
|---|---|
| Site: | Farley |
| Issue date: | 10/30/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20002A293 | List: |
| References | |
| NUDOCS 8011050615 | |
| Download: ML20002A292 (5) | |
Text
.
i f* **
- d UNITTSTA ES NUCLEAR REGU ATORY COMMISSION E*'
o 5
l wAsaiwoTow. o. c. 2 ossa l
ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. l_
AHENDMENT TO FACILITY OPERATING LICENSE Amendment No.16 License No. NPF-2 l.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Alabama Power Cogany (the licensee)datedAugust 15, 1980 supplemented by letter dated September 25, 1980, coglies with the standards and require-ments 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 Comission; 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 Comission's regulations; -
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the healt i and safety of the public; and E.
The issuance of this amendment is P. acr~ dance with 10 CFR Part 51 of the Comission's regulations and aH applicable requirements have been catisfied.
8011050 g
. 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. NPF-2 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.16, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical l
Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
i
\\
Aver i hl. (
teven A. Varga, h'
,0perating Reactor B ar.ch #1
- Division of Licens g
Attachment:
Changes to the Technical Specifications Date of Issuance: October 30, 1980
o' '.
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.16 TO FACILITY OPERATING LICENSE N0. NPF-1 DOCKET NO. 50-348
. Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 2-7 3/4 2-7 6-5 6-5 L
i
, +,
e
P_0WFR, DISTRIBUTION LIMITS SURVElLLANCE REQUIREMENTS (Continued)
WhentheFfislessthanorequaltotheFR limit for the 2.
x appropriatemeasuredcoreplane,additionalpowerd{stribution maps shall be taken and F h compared to FhU and Fxy at least x
once per 31 EFPD.
shallie:imitsforRATEDTHERMALPOWERwithinspecificcoruplanes The F l
e.
RU 1.
F l.71 for all core planes containing bank "D" control x
rods, and 2.
For all unrodded core planes:
RU F
l.68 up to core elevations of 2.4 f t.
U F
$ 1.70 for core elevations from 2.4 ft. to 7.2 ft.
xy Rn F
1.61 for core elevations above 7.2 ft.
xy f.
The F limits of e, above, are not applicable in the following core kane regions as measured in percent of core height from the bottou of the fuel:
1.
Lower core region from 0 to 15%, inclusive.
2.
Upper core region from 85 to 100%, inclusive.
3.
Grid plane regions at 17.8 1 2%, 32.1 1 2%, 46.4 1 2%,
60.6 + 2% and 74.9 + 2%, inclusive.
4.
Core plane regions within i 2% of core height (i 2.88 inches) about the bank demand position of the bank "D" control rods.
C b
g.
With F exceeding F the effects of F on F (Z) shall be xy, xy evaluahdtodetermineifF(Z)iswithin'Lts1mit.
q 4.2.2.1 When F (Z) f s measured pursuant to specification 4.10.2.2, an 9
overali measured F (2) shall be obtained from a power distribution map 0
and increased by 37 to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
FARLEY - UNIT 1 3/4 2-7 Amendment No. J0,16
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Chemistry and Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.*
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976, except for Fire Brigade training sessions which shall be held at least quarterly.
6.5 REVIEW AND AUDIT
- 6. 5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.1 The PORC shall function to advise the Plant Manager on all matters related to nuclear safety.
1 COMPOSITl_0tj j
l 6.5.1.2 The PORC shall be composed of the:
Chairman:
Plant Manager j
Vice Chairman:
Assistant Plant Manager Member:
Technical Superintendent Member:
Operations Superintendent i
Member: (Non-voting)
Plant' Quality Assurance Engineer Member:
Maintenance Superintendent d
i ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than one alter-nate shall participate as voting members in PORC activities at any one time.
- The Minimum qualifications requirement for the Chemistry and Health Physics Supervisor shall become effective when the initial incumbent in this position is replaced.
FARLEY - UNIT 1 6-5 Amendment No, f, TO I
~.
.,