ML20092G730
| ML20092G730 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/14/1995 |
| From: | Matthews D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20092G732 | List: |
| References | |
| NUDOCS 9509200057 | |
| Download: ML20092G730 (8) | |
Text
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UNITED STATES s
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066M001 4
o 4 *.,*g VIRGINIA ELECTRIC AND POWER COMPANY I
DOCKET NO. 50-280 SURRY POWER STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 205 License No. DPR-32 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated November 10, 1994, complies with the standards and requirements 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 i
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 common 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 satisfied.
9509200057 950914 POR ADOCK 05000280 0SG P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-32 is hereby amended to read as follows:
(B)
Technical Specifications The Technical-Specifications contained in Appendix A, as revised through Amendment No.
205, are hereby incorporated in the license. The licensee shall operate the facility in accordance a
l with the Technical Specifications.
I 3.
This license amendment is effective as of its date of issuance and shall i
i be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 422but l
David B. Matthews, Director l
Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
l Changes to the Technical Specifications l
Date of Issuance:
September 14, 1995 l
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sp Moog 21 UNITED STATES y
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20666 4 001
'+9.....,o VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 205 License No. DPR-37 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated November 10, 1994, complies with the standards and requirements 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; 8.
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 health and safety of the public; 4
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 satisfied.
i
)
i
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
(B)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 205, 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 and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION d
David B. Matthews, Director Project Directorate 11-1 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 14, 1995
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 205 TO FACILITY OPfBATING LICENSE NO. DPR-32 AMENDMENT NO. 205 TO FACILITY OPERATING LICENSE NO. OPR-37 DOCKET NOS. 50-280 AND 50-281
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Revise Appendix A as followsi Rcmove Paaes Insert Paaes TS 4.1-7 TS 4.1-7 TS 4.1-8 TS 4.1-8 TS 4.1-8a TS 4.1-8a M
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TABLE 4.1-1 (Continued)
MINIMUM FREQUENCIEOSQH CHECK. CALIBRATIONS. AND TEST OF INSTRUMENT CHANNFI R Channel Desenpton Check Cahbrate 1911 Bemdui 10.
Rod Posmon Bank Counters S(1,2)
N.A.
N.A.
- 1) Each six inches of rod moton O(3) when data loggeris out of sennce
- 2) With analog roj posmon
- 3) For the control banks, the bench-board indicators shaR be checked against the output of the bank eerlap anit.
11.
Steam Generator Level S
R M
12.
Charaing Flow N.A.
R N.A.
13.
Redud Heat Removal Purg Flow N.A.
R N.A.
t 14.
Boric Acid Tank Level
- D R
N.A.
15.
Recuculation Mode Transfer
- a. Refueling Water Storage Tank Level-Low S
R M
- b. Aummatic Actuation Logic and N.A.
N.A.
M E;
Actuation Relays I
16.
Volume ControlTank Level N.A.
R N.A.
n 17.
Reactor Contanment Pressure-CLS
- D R
M(1)
- 1) Isolation valve segnal and spray signal 18.
Boric Acid Control N.A.
R N.A.
m8 19.
Item Deleted l
l o,
E d
- 20. Deisted m
8 L
21.
Contamment Pressure-Vacuum S
R N.A.
4 Pump System
- 22. Steam Line Pressure S
R M
4
TABLE 4.1-1 (Conhnued)
MMMLM FREQUENCIES FOR CHECK. CAI 1RRATIONS. AND TEST OF INSTRI Mr'N CPEr_9 R Channel Dancription Gtledt CaRrata
. Tag Ramasks
- 23. Turbine First Stage Procoure S
R M
24.
tin.s.gency Plan Radation inser.
- M R
M 25.
Erwwonmental Radiation Monitors
- M NA NA TLD Dosameters 26.
Logic ChannelTestin0 NA NA M(1)(2)
- 1) Reactor protection, safety injedion and the consequance limiting safeguards 27.
Turbine C.
, ::j Protection Trip NA R
R system logic channels are tested montNy Channel (Electrical) per this line llem.
- 2) The master and slave relays are not included in the monthly logic channel test of the safety inloction system.
28.
Turbine Trip Selpoint vertication is not applicable 3
A. Stop valve closure NA N.A.
P N
g, B. Low fluid oil pressure NA NA P
a 29.
C*istruc Instrumentation M
R M
g 30.
Reactor Trip Breaker NA NA M
The test shed independently verify
.=
operability at the undervostage and stun trip attachments mo*
31.
Reactor CocM Pressure (Low)
NA R
NA Ea co
TABLE 4.1-1 (Continued)
MINIMW FREQUENCIES FOR CHECK. CAI IRRATIONS. AND TEST OF INSTRNFN r' CHNO2n R Channel Descriptaoq Check Calibrate
.Tmit Remasks l
l 32.
Auxiliary Foodwater l
i
- a. Steam Generator Water Level Low-Low S
R M(1)
- 1) The auto start of the turtune drwen pump is l
not included in the monthly test, but is tested within 30 days prior to each startup
- b. RCP Undervolta0e S
R NA(1)
- 1) The actuation logic and relays are tested wthin 30 days prior to each startup.
- c. S.L (As Safety triection surveillance requirements)
- d. Station Blackout NA R
NA l
- e. Main Feedwater Pung Trip NA NA R
33.
Loss of Power
- a. 4.16 KV Emergency Bus Under-NA R
M ve%ge(Loss of Voltage)
- b. 4.16 KV Emergency Bus Under-NA R
M voltage (Degraded Volta 08) 20 3
34.
Med o
,S' 35.
Manual ReactorTrip N.A.
N.A.
R The test sha8 independently verify the a
operability of the undervoltage and shunt trip attachments for the manual reactor i
trip function The test shat also t..h#y the operabbty of the bypass tweaker trip cirmit.
5 36.
Reactor Trip Bypass Breaker NA NA M(1),
- 1) Remote manual urdervolta0e trip prior R(2) to placing breakerin service.
E
- 2) Automatic undervoltage trip.
e.
y vi g
37.
Safety Irioction input to RPS NA N.A.
R l,]
38.
Reactor Coolant Pump Breaker NA N.A.
R h
Position Trip
-