ML20149D165
| ML20149D165 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/21/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149D170 | List: |
| References | |
| TAC-54452, TAC-54453, NUDOCS 8802090400 | |
| Download: ML20149D165 (15) | |
Text
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UNITED STATES c
NUCLEAR REGULATORY COMMISSION e
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ALA8AMA POWER COMPANY
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DOCKET NO. 50-348 j
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE i
i 4
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Amendment No. 48 License No. NPF-2 4
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Alabama Power Company (the
(
licensee) dated March 1,1984, complies with the standards and j
requirements of the Atomic Energy Act of 1954, as amended (the 3'
Act) and the Comission's rules and regulations set forth in 10 CFR Chapter !*
8 B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; l
C.
There is reasonable assurance: (1)thattheactivitiesauthorizedby
}
this amendment can be conducted without endangering the health and i
safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; 4
)
D.
The issuance of this license amendment will not be inimical to the comon defense and 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 51 of the Comission's regulations and all applicable requirements have been satisfied.
I 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendrent, J
and paragraph 2.C.(2) of Facility Operating License No. NPF-2 is hereby amended to read as follows:
1 i
l W Hsi! WoNA P
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4 2-i (2) Technical Specifications j
The Technical Specifications contained in Appendices j
i A and B as revised through Amendment No. 48, are hereby incorporated in the license. The licensee i
shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSI0h L.
even. Aar/a,W i
Operating Reactor nch #1 Division of Licensing
Attachment:
I Changes to the Technical Specifications Date of Issuance:
September 21, 1984 l
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ATTACHMENT TO LICENSE AMENDMENT fio. 48 AMENDMENT NO.48 FACILITY OPERATING LICENSE NO. NPF-2 l
DOCKET NO. 50-348 Revised Appendix A as follows:
i Remove Pages Insert Pages i
3/4 3-14 3/4 3-14 3/4 6-17 3/4 6-17 3/4 6-18 3/4 6-18 l
3/4 7-82 3/4 7-82 r
6-3 6-3 i
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TABLE 4.3-1 (Continued) 3 TABLE NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.
)
(1)
If not performed in previous 7 days.
2 (2)
Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference greater than 2 percent.
(3)
Compare incore to escore axial flux difference every 31 EFPD.
Recalibrate if the absolute difference is greater than or equal to 3 percent.
(4)
Manual ESF functional input check every 18 months.
(5)
Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.
4 (6)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7)
Below the P-6 (Block of Source Range Reactor Trip) setpoint.
(8)
Logic only, if not performed in previous 92 days.
CHANNEL FUNCTIONAL TEST wiil consist of verifying that each (9) channel indicates a turbine trip prior to latching the turbine i
and indicates no turbine trip af ter latching the turbine.
(10) -
If not performed in the previous 31 days.
i 4
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FARLEY-UNIT 1 3/4 3-14 AttEllDMENT t10. 48 I
- ~
TABLE 3.5-1 (Continued)
ISOLATION Tile m
5 eMn5E A-150 tan 0=
FUNCTION (SEC) g (Cantinued Q
<10 CCW from emc. letdeun RCST Ints 710
- 32. CCW-W-3067 Accumulators fill Itne isoletten Ile 33.
CVC-N-8860 Accumulater tanks sample isoletten valve 718 34.
55-HV-3766 Accumulater tanks sample isolatten valve 710
- 35. 55-W-3334 BCDT vent line isolatten valve 718
- 36. LW-W-7126 RCDT vent line isolation valve IIS 37.
LW-HV-7150 Containment sump recirculatten volve 718 38.
tw-HV-3380
.Deelneralizer water to reacter HD storage 75
- 39. CTS-HV-3659 Containment purge exhaust isolatten valve 35 40.
CSV-W-31%
Containment purge supply 1selatten valvs
<5 41.
CSV-HV-3197 Containment alni-purge enheest 1seletten valve 75 42.
CBV-HV-2867 C Containment mint purge exhaust f selation valve 75 1
- 43. C8V-W-2867 0 Containment elat purge supply isolation valve 44.
CSV-HV-2866 C Containment alni-purge supply isslatten valve 55
- 45. CSV-MW-2866 D y
3.
PHASE *S" 150LATION
CCW-fWW-3052 CCW from RCP ell coolers (15 2.
CCW-MOV-3346 CCW from RCP ell coolers
<10 3.
CCW-MDV-3182 CCW free RCP THAM BARR l
<10 4.
CCW-HV-3184 CCW from RCP THRM BARR
<10 E
5.
CCW-W-3045 Containment lastrument air sagsply valve 3
6.
IA-HV-3611 l
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C.
5AFETY 190ECTION SIGNAL.
<10 Charging pumps to regenerative IRC r
o
<10 1.
CVC-MOV-8107 Chaeging pumps to regenerat!ve HK
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<15 co 2.
CVC-MOV-8108 SW to RCP noter air ccolers
<15 3.
5W-MOV-3135 SW from RCP meter air coolers
<15 4
SW MDV-3131 SW from RCP motor air coolers 5.
i TABLE 3.6-1 (Continued) f ISOLATION TINE
.h U
eQ (SEC)
FUNCTION
.h D.
MANUAL NA Refueling Cavity supply 1.
Q1G11VO12 NA Reactor Coolant drain tank 2.
Q1G21V005*
Reactor coolant LP IC to RHR pump 1A
<120 3.
RHR-MOV-8101A**
<120 Reactor coolant LP IA to RNR pump 1B 4.
AllR-MOV-fl102A*
- NA 5.
QlP18V001" service Air MA 6.
QlP1HV002*
Service Air NA Containment leak rate test valve 1.
C8V-MOV-3238 NA Containment leak rate test valve 8.
C8V-MOV-3239 (17 9.
RHR-MOV-8811 A Containment sump to RHR pump 1A
<l7 10.
RHR-MOV-8811 8 Contairment sump to RHR pump 18
<17 Containment sump to RHR pump 1A 11.
RHR-MOV-8812 A
<17 Containment sump to RHR pump 1B
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12.
RHR-MOV-8812 8
<17 2
13.
C5-MOV-8826 A' C5 pump 1A containment sump suction isolation e
<17 C5 pump 18 containment sump suction isolation 14.
C5-MOV-8826 8
<17 C5 pump 1A containment sump suction isolation e
E 15.
C5-M9V-8627 A
<l7 C5 pump 18 containment sump suction isolation NA l
16.
05-MOV-8827 8 17.
Qt813V0268*
Pressurizer pressure generator NA Containment post-LOCA sampilng valve 1 18.
C8V-MOV-3528 A*
NA Containment post-LOCA sampilng valve 2 19.
CBV-MOV-3528 B*
NA Containment post-LOCA samp11pg valve 3 20.
CBV-MOV-3528 C*
NA Containment post-LOCA sampilng valve 4 21.
C8V-MOV-3528 D*
NA Containment post-LOCA sampilng isolation valve 22.
CBV-MOV-3/39 A*
NA Contalement post-LOCA sampling isolation valve 23.
C8V-MOV-3739 B*
NA Containment post-LOCA sampilng return valve 24.
CBV-MOV-3/45 A*
NA Containment post-LOCA samp11pg return valve 25.
CBV-MOV-3745 B*
NA Containment post-LOCA sampilog return valve k
26.
C8V-MOV-3835 A*
NA Containment post-LOCA sampilng return valve 27.
C8V-MOV-3835 B*
NA g
Containment post-LOCA vent isolation valve
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NA 28.
Containment post-LOCA vent isolat.lon valve g
29.
CBV-NOV-3530" y
5
- May be opened on an intermittent basis under administrattwe controls
- May be opened and power rermved inwier administrative controls when the plant is in se0E 4 (for ensuring overpressure protection system operability).
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PLANT SYSTE!4S 3/4.7.11 FIRE SUPPRESSION SYSTEMS FIRE SUPPRES$10N WATER SYSTEM
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LIMITING CONDITION FOR OPERATION 3.7.11.1 The fire suppression water system shall be OPERABLE with:
a.
Two high pressure pumps, each with a capacity of 2500 gpm, with their discharge aligned to the fire suppression header, b.
Separate water supplies, each with a minimun contained volume of 250,000 gallons, and c.
An OPERABLE flow path capable of taking suction from each tank and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation val.ves to the yard hydrant curb valves, the last valve ahead of the water flow alarm device on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per Specification 3.7.11.2, 3.7.11.4 and 3.7.11.5.
l APPLICABILITY: At all times.
ACTION:
4.
With one of the above required pumps and/or water supplies inoperable, restore the inoperable equipment to ODERABLE status within 7 days or, f
in lieu of any other report required by Specification 6.9.1, prepare j
and submit a Special Report to the Comission pursuant to i
i Specification 6.9.2 within the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system. The provisions of Specifications 3.0.3 and 3.0.4 are not d
applicable.
b.
With the fire suppression water system otherwise inoperable:
1.
Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and i
2.
In lieu of any other report required by Specification 6.9.1, submit a Special Report in accordance with Specification. 6.9 2:
a) By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b) Confinned by telegraph, mailgram or facsimile transmission no i
later than the first working day following the event, and c) In writing within 14 days following the event, outlining the l
action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
FARLEY-UNIT 1 3/4 7-82 AMENDMENT NO.48
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PLANT SYSTEMS 3/4.7.11 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYST5r4
~
LIMITING CONDITION FOR OPERATION 3.7.11.1 The fire suppression water-system shall be OPERABLE with; a.
Two high pressure pumps, each with a capacity of 2500 gpm, with their discharge aligned to the fire suppression header, b.
Separate water supplies, each with a minimun contained volume of l
250,000 gallons, and c.
An OPERABLE flow path capable of taking suction from each tank and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation val.ves to the yard hydrant curb valves. the last valve ahead of the water flow alarm device on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per 4
Specification 3.7.11.2, 3. 7.11.4 and 3.7.11. 5.
l j
APPLICABILITY: At all times.
l j
ACTION:
a.
With one of the above required pumps and/or water supplies inoperable, 1
restore the inoperable equipment to OPERABLE status within 7 days or, in lieu of any other report required by Specification 6.9.1, prepare j
4 and submit a Special Report to the Commission pursuant to d
Specification 6.9.2 within the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
j b.
With the fire suppression water system otherwise inoperable:
1.
Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, i
and l
l 2.
In lieu of any other report required by Specification 6.9.1, l
submit a Special Report in accordance with Specification 6.9.2:
j a) By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b) Confirmed by telegraph, mailgram or facsimile transmission no later than the first working day following the event, and l
c) In writing within 14 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
1 FARLEY-UNIT 1 3/4 7-82 AMENDMENT NO. 48 1
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UNll ED sT ATEs l%
NUCLE AR REGULATORY COMMISSION e<
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wasmNotoN.o c.rosss ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT No. 2 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. NPF-8 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for ary:ndment by Alabama Power Company (the licensee) dated March 1, 1984, complies with the standards and requirements of the Atonic 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, as arrended, the provisions of the Act, and the 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 license amendment will not be inimical to the comen 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 satisfiec.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the a*tachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No, hPF-8 is hereby amended to read as follows:
i
. (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.~39, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h
rga,/
v Ch e
!ven Operating Reactors ch (1 Division of Licensing
Attachment:
~
Changes to the Technical Specifications Date of Issuance: September 21, 1984
ATTACHMENT TO LICENSE AMEN 0 MENT N0. 39 AMENDMENT N0.39 FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Revised Appendix A as follows:
Remove Pages Insert Pages 3/4 3-14 3/4 3-14 3/4 6-17 3/4 6-17 6-3 6-3 4
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i 4
TABLE 4.3-1 (Continued)
TABLE NOTATION With the reactor trip system breakers ciosed and the control rod drive system capable of rod withdrawal.
If not performed in previous 7 days.
(1)
Heat balance only, above 15% of RATED THERKAL POWER. Adjust (2) channel if absolute difference greater than 2 percent.
Compare incore to excore axial flux difference every 31 EFPD.
(3)
Recalibrate if the absolute difference is greater than or equal to 3 percent.
Manual ESF functional input chock every 18 months.
(4)
Each train or logic channel shall be tested at least every 62 (5) days on a STAGGERED TEST BASIS.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(6)
Below the p-6 (Block of Source Range Reactor Trip) setpoint.
(7)
Logic only, if not performed in previous 92 days.
(8)
(9) - CHANNEL FUNCTI0t4AL TEST will consist of verifying that each channel indicates a turbine trip prior to latching the turbine and indicates no turbine trip af ter latching the turbine.
(10) - If not performed in the previous 31 days.
FARLEY-UNIT 2 3/4 3-14 AMENDMENT NO. 39
l l
TABLE 3.6-1 (Continued)
S ISOLATION TIME (SEC) k PHASE "A" ISOLATION FUNCTION
-f (Continued E
<10 d
a CCW from exc. letdown RCOT HMS 310
- 32. CCW-HV-3067 Accumulators fill line isolation
<10 33.
CVC-HV-8860 Accumulator tanks sample isolation valve 710 u
l 34.
SS-HV-3766 Accumulator tanks sample isolation valve 710 35.
SS-HV-3334 RCDT vent line isolation valve 710 36.
LWP-HV-7126 RCDT vent line isolation valve 710 37.
LWP-HV-7150 Containment sump recirculation valve 710 38.
LWP-HV-3380 Demineralizer water to reactor H0 storage 75 39.
CTS-HV-3659 Containment purge exhaust isolation valve 75 40.
Containment purge supply isciation valve 75 41.
C8V-HV-3197 Containment mini-purge exhai.st isolation valve 42.
C8V-HV-2867 'C Containment mini purge exhaust isolation valve 35
<5 R
- 43. C8V-HV-2867 D Containment mini purge supply isolation valve
<5
- 44. C8V-HV-2866 C Containment mini purge supply isolat.fon valve T
45.
C8V-HV-2866 0 0
8.
PHASE "B" ISOLATION
<15 i
<15 1.
CCW-MOV-3052 CCW from RCP oil coolers
<15 l
2.
CCW-MOV-3046 CCW from RCP oil coolers
<10 3.
CCW-MOV-3182 CCW from RCP THRM BARR
<10 4.
CCW-HV-3184 CCW from RCP THRM BARR
<10 5.
CCW-HV-3045 Containment instrument air supply valve i
6.
IA-HV-3611 g
5x C.
SAFETY INJECTION SIGNAL g
Charging pumps to regenerative HX
<10
<10 1.
CVC-MOV-8107 Charging pumps to regenerative HX
<15 i
2.
CVC-MOV-8108 SW to RCP motor air coolers
<15 3.
SW-MOV-3135 g
<15
)
4.
SW-MOV-3131 SW from RCP motor air coolers f
5.
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Tedmical Anninistrative Training Sys. Perf. at!
Sgrrintmimt Superintmient Superint m knt l
Superintmimt Director Plarming Super.
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Tecimical Q erati m s 1 IAC Maintenance Plaming Sys. Perf.
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Sgervisor sgervisor Spervisor Supervisor Supervisor Supervisor Supervisor l
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9fft R IAC Maintenance Supervisor Forwun Formunn Engineer Nrshall**
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Qaalliy Omtrol l
Supervisor Supervisor I I I
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Cheuristry & Invironmental Staff Staff Sapervisor***
Supervisor Afvisor I
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- 1. - Senior (herator's License Staff Staff
- - Reactor (5erators will have Operator's License
- - Onsite bsponsibility for Fire Protection Prayan Figsre 6.2-2 facility Oryntzatim
- In routire sutters, ttu' Ilealth Ptysics Spervisor repyts directly to tie Tahnical Sgerintenrient. In matter of rarliation policy determination, fr.terpretatie or implementation (Based y the Health Physic Supervisor *s judgent) the Health Physics Sqervisor any rnort directly to the Assistant Plant knager.
Farhy - thit 2 6-3 MMNT NO. 39 l
4
- - -