ML17263A248
| ML17263A248 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/20/1993 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17263A249 | List: |
| References | |
| NUDOCS 9304270308 | |
| Download: ML17263A248 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.
E.
GINNA NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No.
DPR-18 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Rochester Gas and Electric Corporation (the licensee) dated October 15,
- 1990, as supplemented March 5,
- 1991, November 30,
- 1992, and April 5,
- 1993, 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.
D.
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; 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 2.
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.
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-18 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
52
, are hereby incorporated in the
- license, The licensee shall operate the facility in accordance with the Technical Specifications.
9304270308 930422 PDR ADOGK 05000244 PDR
3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 20, 1993 Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
ATTACHMENT 'TO LICENSE AMENDMENT NO.
52 FACILITY OPERATING LICENSE NO.
DPR-18 DOCKET NO, 50-244 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3.6-4 3.6-6 3.7-7A 3.6-10 3.6-4 3.6-6 3.6-7A 3.6-10
TABLE 3.6-1 CONTAINMENT ISOLATION VALVES PENT.
NO 29 IDENTIFICATION/DESCRIPTION Fuel Transfer tube 100 Charging line to "B" loop 101 SI Pump 1B discharge
'113 SZ Pump lA discharge 120 Nitrogen to Accumulators 120 Pressurizer Relief Tank (PRT) to Gas Analyzer (GA) 102 Alternate charging to "A" cold leg 103 Construction Fire Service Water 105 Containment Spray Pump lA 106 "A" Reactor Coolant Pump (RCP) seal water inlet 107 Sump A discharge to Waste Holdup Tank 108 RCP seal water out and excess letdown to VCT 109 Containment Spray Pump 1B 110 "B" RCP seal water inlet 110 SI test line 111 RHR to "B" cold leg 112 Letdown to Non-rcgen.
Heat Exchanger ISOLATION BOUNDARY flange CV 370B CV 889B CV 870B CV 383B welded flange CV 862A CV 304A AOV 1728 MOV 313 CV 862B CV 304B MV 879 MOV 720 (20)
AOV 371 CV 889A CV 870A CV 8623 AOV 539 MAXIMUM ISOLATION TIME *(SEC)
NA NA NA NA NA NA NA NA 60 60 NA NA NA NA 60 NA NA NA 60 ISOLATION BOUNDARY (1)
(2)
(5)
(5)
(2)
MV 5129 (3)
(2)
AOV 1723 (4)
(3)
(2)
(5)
(6)
AOV 200A AOV 200B AOV 202 RV 203 (5)
(5)
AOV 846 MV 546 (7)
MAXIMUM/
ISOLATION TIME
- (SEC)
NA NA NA NA NA NA NA NA 00 NA NA NA NA NA 60 60 60 NA NA NA 60 NA
Pg PENT.
gs NO.
141 142 0
143 IDENTIFICATION/DESCRIPTION RHR-tl pump suction from Sump B
RHR-k2 pump suction from Sump B
RCDT pump suction ISOLATION BOUNDARY MOV 850A (13)
MOV 850B (13)
AOV 1721 MAXIMUM ISOLATION TIME *(SEC)
NA NA 60 ISOLATION BOUNDARY MOV 851A (13)
MOV 851B (13)
ISOLATION TIME
- (SEC)
NA NA 60 60 201 Reactor Compart. Cooling Unit A 6 B
202 "B" Hydrogen recombiner (pilot 8 main) 203 Contain. Press.
Transmitter PT-947 6 948 203 Post accident air sample to "B" fan MV 4757 (16)
MV 4636 (16)
MV 1076B MV 1084B PT 947 PT 948 MV 1563 MV 1566 NA NA NA NA NA NA NA NA (ll)
(11)
SOV-IV-3B SOV-IV-5B MV 1819C MV 1819D MV 1565 MV 1568 NA NA NA Normally Clos~
NA Normally Clos~
NA NA NA NA 4J Ch I
204 Shutdown Purge Supply Duct [Purge Supply Duct]
205 Hot leg loop sample 206 Przr. liquid space sample 206 "A" S/G sample 207 Przr.
Steam space sample 207 "B" S/G sample 209 Reactor Compartment.
Cooling Units A & B 210 Oxygen makeup to A 6 B recombiners flange (22)
[AOV 5870]
AOV 966C AOV 966B AOV 5735 AOV 966A AOV 5736 MV 4758 (16)
MV 4635 (16)
MV 1080A 60 60 60 60 60 NA NA NA MV 956D (14)
MV 956E (14)
(17)
MV 956F (17)
(11)
(11)
[5]
AOV 5869 (22) 5 NA NA NA NA NA NA.
NA NA Normally Closed NA Normally Closed
PENT NO.
g 315 316 g
O 317 318 319 320 IDENTIFICATION/DESCRIPTION Service Water from "C" fan cooler Service Water to "B" fan cooler Leakage test supply Dead weight tester (decomissioned)
Service Water from "A" fan cooler Service water to "C" fan cooler 4)
Ch I
332 Leakage test and hydrogen monitor instrumentation lines 321 A S/G Blowdown 322 B S/G Blowdown 323 Service Water from "D" fan cooler 324 Demineralized water to Containment 332 Cont. Press.
Trans.
PT-944, 949
& 950 ISOLATION BOUNDARY MV 4643 (16)
MV 4628 (16) flange welded shut MV 4629 (16)
MV 4647 (16)
AOV 5738 AOV 5737 MV 4644 (16)
CV 8419 PT 944 PT 949 PT 950 MV 7448 MV 7452 MV 7456 SOV 921 SOV 922 SOV 923 SOV 924 HAXIMUM ISOLATION TIME *(SEC)
NA NA NA NA NA NA 60 60 NA NA NA NA NA NA NA NA NA NA NA NA ISOLATION BOUNDARY (11)
(11)
MOV 7443 welded shut (11)
(11)
(17)
(17)
(11)
AOV 8418 MV 1819G MV 1819F MV 1819E cap cap cap (21)
(21)
(21)
(21)
MAXIMUM/
ISOLATION TIME
- (SEC)
NA NA NA Normally Closed NA NA NA NA NA
,NA NA NA NA NA NA NA NA NA NA NA NA
(10)
(11)
(12)
(13)
(14)
(15)
(16)
(17)
The pressure transmitter provides a boundary.
1 Normally operating incoming and outgoing lines which are connected to closed systems inside containment and protected against missiles throughout their length, are provided with at least one manual isolation valve outside containment (FSAR 5.2.2 pg. 5.2.2-2).
The single remotely controlled containment isolation valve is normally open and motor operated.
The cooling water return line is not directly connected to the reactor coolant system and, should remain open while the coolant pump is running.
A second automatic isolation barrier is provided by the component cooling water loop, a closed system.
(FSAR 5.2.2 pg. 5.2.2-la)
See FSAR Table 5.2.2-1 'and Figure 5.2.2-2.
Sump lines are in operation and filled with fluid following an accident.
Containment leakage testing is not required.
The valves are subjected to RHR system hydrostatic test.
Normally operating outgoing lines connected to the Reactor Coolant System are provided with at least one automatically operated trip valve and one manual isolation valve in series located outside the containment.
In addition to the isolation
- valves, each line connected to the Reactor Coolant System is provided with a remote operated root. valve located near its connection to the Reactor Coolant System.
(FSAR 5.2.2 pg.
5.2.2-1)
See FSAR Table 5.2.2-1 and Figure 5.2.2-17.
The Service Water system operates at a pressure higher than the containment accident pressure and is missile protected inside containment.
Therefore, these valves are used for flow control only and need not be leak tested.
The S/G tubes and secondary side provide a closed system inside containment.
(18) Fire Service Water will be used only to fight fires inside containment.
AOV 9227 is closed during power operation.
A containment isolation signal to automatically close this valve is not required because a spurious signal during a fire may be hazardous to personnel and may impede fire suppression activities.
(19)
(20)
See FSAR Table 5.2.2-1 and Figure 5.2.2-16.
Containment leakage testing is not required per L. D. White, Jr. letter to Dennis L. Ziemann, USNRC dated September 21, 1978.
Amendment No.
52 3.6-10