ML19351F321
| ML19351F321 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/10/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19351F319 | List: |
| References | |
| NUDOCS 8101120232 | |
| Download: ML19351F321 (10) | |
Text
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UNITED STATES s
NUCLEAR REGULATORY OMMISSION
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WASHINGTON. D C.206S5 t
ALABAMA POWER COMP ANY
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DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 1 A'*EMOMENT TO FACILITY OPERATING LICENSE Amendment No.17 '
License No. NPF-2 1.
The Nuclear Regulatory Commission (tne Commission) has found that:
A.
The aoplications for amendment by Alabama ?cwer Cocany (the licensee) dated October 15,1979 (modified by letter dated October 3,1980) and Oc.ober 23, 1979, in addition to the licensee's filing dated March 23, 1979, as revised Oct:ber 8,1979 and Mar:n 20, 1980, comely with the standards and requirements of the Atomic Energy Act of 1952, as amended (the Act) and the Conunission's rules and regulations set for-h in 10 CFR Chapter I; 3.
The facility will coerate in conformity with the a: plication and filing, the previsions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authori:ed by.:his amendment can be c:nducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with :ne C =ission's regulations; D.
The issuance of this amendment will not be inimical to the c =cn defense and security or :c the heal:n and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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4 2-1 2.
Accordingly, the license is amended by changes to tne 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 Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.17. are hereby incoroorsted in the license. The licensee shall 4
operate the facility in accordance with the Technical Specifications.
(3) Redesignate paragaph 2.D as 2.0.(1) and add paragraph 2.0.(2) to read as follows:
2.D.(2) The licensee shall fully imolement and maintain in effect all provisions of the Commission-approved Safeguards Contingency Plan, including amendments and changes made pursuant to the authority o# 10 CFR 50.5a(p).
The aoproved Contingency Plan consists of documents withheld from cublic disclosure pursuant to 10 CFR 2.790(d) identified as " Joseph M. Farley Safeguards Contingency Plan" dated March 23, 1979 as revised October 8,1979 and March 20, 1980, submitted pursuant to 10 CFR 73.40.
The toct ngency Plan was to have been fully implemented, i
in accordance with 10 CFP. 73.40(b), within 30 days of the accroval by the Commission which was dated May 1, 1900.
3.
This license amendment is effective as of the date of its issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION
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- 1 Division of Licensing
Attachment:
Changes to the Technical Soecifications Oate of Issuance: December 10, 1980 l
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ATTACHMENT TO LICENSE AMENDMENT AMENOMENT NO.17 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-348 Revise Ascendix A as follows:
Remove Pages Insert Pages XVIII XVIII 3/4 3-30 3/4 3-30 1
6-19 6-19 6-20 6-20 6-21 l
l INDEX ADMINISTRATIVE CONTROLS SECTIGN PAGE 6.1 RESPONSIBILITY..............................................
6-1 6.2 ORGANIZATION 0ffsite.....................................................
6-1 Fa c i l i ty S ta f f..............................................
6-1 6.3 FACIL ITY STAFF QUAL IFICATIONS...............................
6-5 6. /.
TRAINING....................................................
6-5 6.6 REVIEW AND AUDIT 6.5.1. PLANT OPERATIONS REVIEW COMMITTEE (PCRC) runction..................................................
6-5 Co m o o s i ti o n...............................................
5-5 A1:ernates................................................
6-5 Meeting Frequency.........................................
6-6 uorum....................................................
6-6 Responsibilities..........................................
6-6 Authority.................................................
6-7 Records...................................................
6-7 6.5.2 NUCLEAR OPERATIONS REVIEW BOARD (NORB) f u nc ti o n..................................................
0-r C om o o s i t i o n...............................................
6-8 A l t e rn a te s................................................
5-8 FARLEY - UNIT 1 XV I
INDEX l
ACHINISTRATIVE CONTROLS PAGE SECTION C o n s u l ta n ts.................................................
6-8 6-8 Meeting Frequency...........................................
6-9 Quorum......................................................
6-9 Review......................................................
6-10 Audits......................................................
5-10 A u tn o r i ty...................................................
5-10 Records.....................................................
6.5.3 TECHNICAL REVIEW AND CONTR0L..............................
6-11 il si -- - O n A B i e OC u-, r R3. u-Av I 0 N................................
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s j 6.7 SAFE Y L IM IT 7 IOLAiION......................................
6-13 k
ys.sPR0CEcuREs..i....!.........................................
6-13 si El
'!. 5.9 REPORTING REJU!REMENTS 1
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.I Il6.9.1 ROUTINE REPORTS AND RE?0RTABLE OCCURRENCES................
6-14 h
5-17 NG.9.E SPECIALRE?0RTS...........................................
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6-18 RECORD RE ENTICN...........................................
ll 3.10
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't 5-19 it 5 il RADIATION PROT:C'*0N PR0 GRAM...............................
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1-6-19
!. 6.12 u!GM RADIAT'ON AREA........................................
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'!. l) 6.13 EliVIRONMENT AL Q UALIFICAT T_ON........................
5-20
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,,FARLEY - UNIT 1 XVIII Order dated Oc ooer 21, 1980 AMENDMENT NO.17 i
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 7.
Containment Pressure--High-High a.
Steam Line Isolation 1 7.0 8.
Containment Pressure--High-Hich-High a.
Containment Spray 1 45.0 b.
Containment Isolation-Phase "B" Not Applicable 9.
Steam Generator Water Level--High-High a.
Turbine Trip-Reactor Trip 1 2.5 b.
Feedwater Isolation 1 32.0 10.
Steam Generator Water Level--Low-Low a.
Motor-driven Auxiliary Feedwater Pumps **
60.0 b.
Turbine-driven Auxiliary Feecwater ' umps ***
60.0
- 11. Undervoltage RCP a.
Turbine-driven Auxiliary 60.0 l
l 12.
S.I. Signal a.
Motor-driven Auxiliary Feedwater Pump 60.0
- 0n 2/3 Any Steam Generator
- 0n 2/3 in 2/3 Steam Generators l
1 FAR:.EY - UNIT 1 3/4 3-29 i
TABLE 3.3-5 (Continued)
TABLE NOTATION
- Diesel generator starting and sequence loading delays included.
Response time limit includes opening of valves to establish SI path and attainment of discharge cressure for centrifugal charging pumps and RHR pumps.
f Diesel generator starting-and sequence loading delays not included.
Offsite power available. Response time limit includes opening of valves to establish SI-path and attainment of discharge pressure for centrifugal charging pumps.
ff Diesel generator starting and sequence loading delays included.
Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging-pumps.
fif Verification shall include testing ~ of all instrumentation, the isolation valves (MOV-3232A, 32323, 3232C), the control valves (FCV-478,488,4981 and the bypass valves (FVC 479, 489, 4991. The isolation valves must function within 30 seconds and the control valves and bypass valves within 5 seconds.
FARLEY - UNIT 1 3/4 3-30 AMENDMENT NO. 17 CA-
ADMINISTRATIVE CONTROLS e.
Records of gaseous and liquid radioactive material released +4 the environs.
f.
Records of transient or coerational cycles for those facility components identified in Table 5.71.
g.
Records of reactor tests and equipeents.
h.
Records of training and qualification for current embers of the plant staff.
Records of i.-service inspections performed cursuant to these I 1.
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Technical Specifications.
- j. Records of Quality Assurance activities required by the QA Manual.
k.
Records of reviews performed for changes made to procedures or equiement or reviews of tests and experiments pursuant to 10 CR 50.59.
1.
Records of meetings of the PORC and the NORB.
m.
Records of secondary water sampling and water quality.
n.
Records for Environmental Cualification which are covared under the provisions of paragraph 6.13.
5.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be precared consistent with the requirements of 10 CFR Part 20 and shall be aporoved, maintained and adhered to for all operations involving personnel radiation exposure.
5.12 HIGH RADIATION AREA 5.12.1 In lieu of the " control device" or " alarm signal" reoutred by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 erem/hr but less than 1000 -
mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).*
An individual or group of individuals cermitted to enter such areas shall be ;rovided with one or more of the following:
Sealtn shysics personnel or cersonnel escorted by health :hysics cersonnel shall be exemot from the RWP issuance recuirement during the per#ormance of their assigned radiation protection duties, provided they are following plar.. radiation protection procedures for entrj in'a hign radiation areas.
=ARLEY - UNIT 1 5-19 AMENCMENT NO. 3, A, 17 Order dated October 24, 1980
ADMINISTRATIVE CONTROLS a) A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b) A radiation monitoring device which continuously integrates the radiation dose rate in the area and alanns when a pre-set integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have Leen established and personnel have been made knowledgeable of them.
c) A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive exposure control over the activities within the area and who will perform periodic radiation surveillance at the frequency specified in the RWP. The surveillance frequency
)
will be established by the Health Physics Supervisor.
6.12.2 In addition to the requirements of 6.12.1, areas with radiation levels greater than 1000 mrem /hr shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift foreman and/or health physics supervision. Doors shall remain locked except during parfods of access by personnel under an approved Radiation Work Permit (RWP) which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas with radiation levels in excess of 1000 mrem /hr* that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, con-spicuously posted and a flashing light shall be activated as a warning device.
In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.
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6.13 ENVIRONMENTAL QUALIFICATION 6.13.1 By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the pro-visions of: Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class lE Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588 " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment,"
December 1979. Copies of these documents are attached to the Order for Modification of License No. NPF-2 dated October 24, 1980.
' Measurement mace at 18" from source of radioactivity.
FARLEY - UNIT 1 6-20 AMENDMENT NO. 3,17 Order dated October 24, 1980 l
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i ADMINISTRATI'/E CONTROLS 6.13.2 By no later than December 1,1980, complete and auditible records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.
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i FARLEY - UNIT 1 6-21 AMENDMENT NO.17 l
Order dated October 24, 1980
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