ML19331B710
| ML19331B710 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley, Nine Mile Point, Indian Point, North Anna, Turkey Point, Crystal River, Ginna, Farley, San Onofre, Berkeley Research Reactor  |
| Issue date: | 04/15/1980 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Sauter G NRC COMMISSION (OCM) |
| References | |
| FOIA-80-303, FRN-45FR36082, RULE-PR-50 NUDOCS 8008120647 | |
| Download: ML19331B710 (2) | |
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UNITED STATES y Q.r > ( 3 p,
NUCLEAR REGULATORY COMMISSION 3g aE WASHINGTON. D. C. 205SS
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APR 151980 NOTE T0:
George Sauter, Technical Assistant FROM:
G. Lainas, Chief, Plant Systems Branch, DDR In our telecon of April 9,1980, you requested that we provide the following:
1.
Documentation that establishes the completion dates for the alternate shutdown systems at Indian Point 2 and 3, Beaver Valley 1, Crystal River 3, Farley 1, and North Anna 1; and 2.
Documentation that establishes completion dates for fire protection modifications on R.E. Ginna, Turkey Point 3/4, Nine Mile Point, and San Onofre 1.
Per our telecon, I am providing as Enclosures 1 and 2, responses to the above requests.
ldo:
G. Lainas, Chief
,/ Plant Systems Branch Division of Operating Reactors cc w/ enclosures:
D. Eisenhut R. Ferguson T. Wambach 7
THIS DOCUMENT CONTAINS POOR QUAUTY PAGES 8008120647
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SDUTHERN CALIFORRIA EDISON COMPANY AND SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 4t,
' License No. DPR-13 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The facility will operate in conformity with the license amencinent, the provisions of the Atomic Energy Act of 1954, as amended (the Act), and the rules and regulations of the Commission; B.
There is reascnable 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; C.
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 j
D.
The issuance of this amendment is in accordance with 10 CFR Part Sl.of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by changing paragraph 3.B and adding paragraph 3.H to Provisional Operating License No. DPR-13 to read as follows:
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2 Technical Specif'ications B.
The Technical Specifications contained in Appendices A and'B, as revised through Amendment No.
44, are The licensee hereby incorporated in the 1-icense.
shall operate the facility in accordance with the
< Technical Specifications.
H.
Fire Protection
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The licensee.may proceed with and is required to complete the modifications identified in Paragraphs 3.1.1 through 3.1.17 of the NRC's Fire Protection 19,.1979 Safety Evaluation (SE), dated July These modifications sill be for the f acility.
completed in accordance With the schedule in Table 3.1 of the SE and supplements thereto.
In addition, the licensee shall submit the additional information identified in Table 3.2 of this SE in In accordance with the schedule contained therein.
the event these dates fo.r subnittal cannot be met, the licensee shall submit a report, explaining the circumstances, together with a revised schedule.
The licensee is required to implement the administrative The controls identified in Section 6 of the SE.
administrative controls shall be in effect within 90 days from the date of issuance of this amendment.
This license amendment is effective as of the date of 3.
FOR THE NUCLEAR REGULATORY C0KMIS M
' Q Dennis L. Ziemann, Chief Operating Reactors B. ranch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance. 7/1gj79
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l 7 - ~. m _ ____ Table 3.1 J,,,,a3 f,
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imolementation Schedule l
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',Le-Intecrated with By End of Core 8 Refueline*
f Others 3.1.1(1) and (5) 1.
Fire Detection 1
l None 3.1.2 I
Fire Water Supply l
2.
None 3.1. 3 I
3.
Yard Hydrants f
3.1.4 None hose Stations (a) f 4.
Others for Area 9A k'ater Suppression Systems 5.
None 3.1.6 Foam Suppression Systems-6.
For 480v Room for 4Kv Room I
Gas Suppression Sfstems l
7.
None 3 l1. 8' l
Portable Extinguishers (b)-
f
' None a.
3.1.9 S.
Fire Doors None 3.1.10 Supervision of fire Doors (c) 10.
Between Test Pump and Fire Barriers (c)
Charcing Pump.
At In other Areas 11.
j North Wall of Area 9A.
j In Control Room In other Room:
12.
Fire Dampers Ventilation Opening.
l 3.1.13(1), (2) and Othe.s Fire Barrier Penetrations
-(5) 13.
3.1.14 None
'a'ater Damage Protection None 14.
3.1.15 S
75.
Control of Combustibles c
None 3.1.16
' i 6.
Isolation Devices None
~3.1'.17 -
Frergency Lighting (d) 17.
i nt associate
'P.esently scheduled for Spring 1980.
ine items in column " Integrated with SEP" are not needed to protect equ witr. the existing safe shutdown capability.
possible modifications resulting from the ongoing
' tiers nay be imoacted b)y The staff concurs.
fire orotection modifi-Eva".uation Program (SEP.will insure en integrated long-tem resolution of these the SED cations with the results f rom our SEP review.
!a' P-essure Test Hose Station (s) - Completed o', Co.oleted
.:, Cstpleted
.4 har.dlights - Completed 3-2
ENCLOSURE 1
'S 4
ALTERNATE SHUTDOWN SYSTEMS 1
j SCHEDULED TO BE COMPLETED BY DECEMBER 1980 i
Indian Point 2:
License' condition: End of 1980 refueling, (scheduled for 12/80)
Indian Point 3:
License Condition: October 31, 1980.
Farley 1:
License Condition: End of 2nd refueling, (scheduled for 11/80)
Crystal River 3: License Condition:
October 1980 (letter clarifies it will be 10/31/80).
Beaver Valley 1: License Condition: October 31, 1980.
North Anna 1:
License Condition: End of 2nd refueling, but not later than May 1981 (current estimate is 12/80).
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UNITED STATES 4
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NUCLEAR REGULATORY COMMisslON t
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W ASHINGTON. D. C. 205E6 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R. E. GINNA NUCLEAR POWER PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 24 License No. DPR-18 The Nuclear Regulatory Commission (the Commission) has found that:
1.
The facility will operate in confonnity with the license amendment, the provisions of the Atomic Energy Act of 1954, A.
as amended (the Act), and the rules and regulations of the Commission; There 'is reasonable assurance (i) that the activities authorized B.
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities l
will be conducted in compliance with the Commission's regulations.;
The issuance of this amendment will not be inimical to the 1
C.
common defense and security or to the health and safety of the public; and he issuance of this, amendment is in accordance with 10 CFR Part D.
I of the Commission s regulations and all app 1icab1e requirements have been satisfied.
Accordingly, Provisional Operating License No. DPR-18 is hereby 2.
amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by changing paragraph 2.C.(2) and adding paragraph 2.C.(5) to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 24, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Tech 71 cal Specifications.
(5)
Fire Protection The licensee may proceed with and is required to complete the modifications identified in Paragraphs 3.1.1 through 3.1.49 of the NRC's Fire Protection Safety Evaluation (SE) dated February 14,1979, on the facili ty.
These modifications will be completed in accordance with Table 3.1 of the SE and supplements thereto.
In addition, the licensee shall submit the additional information identified in Table 3.2 of this SE in accordance with the schedule contained therein.
In the event these dates for submittal cannot be met, the licensee shall submit a report, explaining the circumstances, together with a revised schedule.
The licensee is required to ! Jplement the administrative controls identified in Section 6 of the SE. The administrative.
controls shall be in effect immediately, except for those modifications indicated in Section 3.1 of the SE, which shall become effective on the dates indicated in Table 3.1 of the SE.
This license amendment is effective as of the date of its issuance.
3.
FOR THE NUCLEAR REGULATORY COMMISSION
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- iW,-ev Dennis L. Ziemann, Chi Operating Reactors B ch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: February 14, 1979
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TABLE 3.1 IMPLEMENTATION DATE FOR MODIFICATIONS ITEMS DATE 3.1.1 Fire Detection 5ystems...................................
12/80
3.1.2 Water Suppression Systems and Equipment..................
6/81 '
3.1.3 Gas Suppression Systems and Equipment....................
6/81
3.1.4 Curbs....................................................
7/79
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3.1.5 Fire Doors...............................................
12/79 3.1.6 Computer Room Ceiling....................................
6/79 3.1.7 Water Spray Shields......................................
6/81' 3.1.8 Fire Barriers............................................
6/80 3.1.9 Fire Dampers.............................................
6/81 "
3.1.10 Halon Storage............................................
complete -
3.1.11 Battery Room Ventilation.................................
6/80 3.1.12 Fire A1 arms..............................................
12/80
3.1.13 Relocation of Gas Meter..................................
7/79 3.1.14 Diesel Generator Room Manhole Covers.....................
complete 3.1.15 Flame Retardant Cable Coating............................
complete 3.1.16 Door Closure Adjustment..................................
complete 3.1.17 Turbine Oil Reservoir Area...............................
9/79 3.l.18 P hy s i c a l Ex a m i n a t i o n.....................................
complete 3.1.19 Diesel Room Water Suppression System.....................
6/81 <-
3.1.20 Service Water Piping in Diesel Room......................
9/79 3.1.21 Control Room Separation..................................
6/80 3.1.22 Exterior Hydrants................................'........
6/79 3.1.23 Eme r g e n cy Li g h t s.........................................
6/79 3.1.24 Piping and Duct Penetrations.............................
12/79 3.1.25 Construction Joints......................................
12/79 3.1.26 Exterior Hose Houses.....................................
6/79 3.1.27 Special Purpose Fire Fighting Equipment..................
6/79 3.1.28 Fire Fighting Equipment Storage..........................
6/79 3.1.29 Diesel Fire Pump Testing and Surveillance................
complete 3.1.30 Fire Door Supervision....................................
3/79 3.1.31 Brigade Training.........................................
9/79 3.1.32 Control of Combustibles..................................
2/79 3.1.33 Control of Ignition Sources..............................
2/79 3.1.34 Prefire Strategies.......................................
12/79 3.1.35 O f f-D u ty B ri ga de Re c a 11..................................
complete 3.1.36 Hose Stretch Tests.......................................
2/79 6/81 '
3.1.37 F i r e D amp e r s.............................................
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l TABLE 3.1 (Continued)
ITEMS DATE 3.1.38 Fire Barriers............................................
6/79 3.1.39 Reactor Coolant Pump Lube Oil Collection System..........
6/81 '
3.1.40 Fire Water Piping System.................................
12/80 e 3.1.41 Manual Hose Stations Inside Containment..................
6/81 -
3.1.42 Signaling Circuits Supervision...........................
12/80 '
3.1.43
' Detector Testing.........................................
12/80 '
3.1.44 Exterior Hydrant Freeze Protection.......................
6/79 3.1.45 Working Permi t Involving Ignition Source.................
2/79 3.1.46 Auxiliary Boiler.........................................
9/79 3.1.47 Transient Combustibles...................................
12/79 3.1.48 Hydrogen Piping..........................................
6/80 3.1.49 Kitchen Area.............................................
6/80 9
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