ML20080D137
| ML20080D137 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/31/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080D141 | List: |
| References | |
| NUDOCS 8402080506 | |
| Download: ML20080D137 (5) | |
Text
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fo, UNITED STATES
{ ' ),. y',g NUCLEAR REGULATORY COMMISSION 3.a,
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WASHINGTON, D. C. 20555 Y
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
94 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 August 25, 1983, 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 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 reouirements have been satisfied.
8402080506 040131 PDR ADOCK 05000280 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.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:
8.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 94
, 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 the date of :ts issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
{ h'
. V r,ga, Chi f ven perating Reactors nch No. 1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
JAN 3 I 1984
Warc
)c, UNITED STATES f - ) p q (
,p, NUCLEAR REGULATORY COMMISSION 3.k 1%,
/E WASHINGTON, D. C.10555
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE 93 Amendment No.
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 (thelicensee)datedAugust 25, 1983, 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.
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.
4
. 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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 93
, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
_1
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Operating Reactors B nch No. 1 Division of Licens~n
Attachment:
Changes to the Technical Specifications Date of Issuance:
JAN 3 1 1984
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT N0.
94 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO.
93 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 2 -
Revise Appendix A as follows:
Remove Pages Insert Pages 4.17-17 4.17-17 4.17-29 4.17-29 4.17-41 4.17-41 6.4-2 6.4-2 J
i i
4
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TABLE 4.17-1 i
UNIT NO. 1 SUPPRESSOR DATA RADIATION REMOVAL SYSTEM DESIGNATION SIZE
' LOCATION ACCESSIBILITY CATB'.ORY CATEGORY l
Aux. Faed System 1-WAPD-HSS-140 1 1/2" Containment Operating Level I
H R
i l
Aux. Feed System 1-WAPD-HSS-141A 1 1/2" Containment Operating Level I
H R
l Aux. Feed System 1-WAPD-HSS-141B 1 1/2" Containment Operating Level I
H R
I i
Aux. Feed System 1-WAPD-HSS-142 1 1/2" Containment Operating Level I
H R
Aux. Feed System 1-WAPD-HSS-143A 1 1/2" Containment Operating Level I
H R
Aux. Feed System 1-WAPD-HSS-143B 1 1/2" Containment Operating Level I
H R
l Aux. Feed System 1-WAPD-HSS-146 1 1/2" Safeguards A
N R
l Aux. Feed System 1-WAPD-HSS-148 1 1/2" Safeguards A
N, R
l i
i j
a 8
n 1
O d
i a
e 5
LO W
4 1
l TABLE 4.17-1 1
UNIT NO. 1 SUPPRESSOR DATA
]
l RADIATION REMOVAL SYSTEM DESIGNATION SIZE LOCATION ACCESSIBILITY CATEGORY CATEGORY Make-up System 1-WCMU-HSS-100 1 1/2" Safeguards A
N R
Containment Spray System 1-CS-ilSS-01 1 1/2" Safeguards Basement A
N R
Service Water System 1-SW-HSS-2 PSA-1/4 Machinery Room f3 A
N D
I S/G Blowdown 1-WGCB-HSS-10 1 1/2" Aux. Basement A
N R
S/G Blowdown 1-WGCB-MSS-23 PSA-3 Aux. Basement A
N D
l S/G Blowdown 1-WGCB-MSS-11 PSA-1/2 A Loop room-E1. 13/6" I
H D
)
S/G Blowdown 1-WGCB-MSS-12 PSA-1/2 A loop room-El. 7'8" I
H D
S/G Blowdown 1-WGCB-MSS-13 PSA-1/2 A loop room-El. 8'3" I
H.
D S/G Blowdown 1-WGCB-MSS-14A PSA-1/2 A loop room-El. 6' I
H D
S/G Blowdown 1-WGCB-MSS-145 PSA-1/2 A loop room-El. 6' I
H D
S/G Blowdown 1-WGCB-MSS-15A PSA-1/2 A S/G Cubicle I
H D
S/G Blowdown 1-WGCB-MSS-15B PSA-1/2 A S/G Cubicle I
H D
q
/G Blowdown 1-WGCB-MSS-16 PSA-1/2 A S/G Cubicle I
H D
Mi/G Blowdown 1-WGCB-MSS-17A PSA-1/2 B loop room-El. 13' I
H D
3/GBlowdown 1-WGCB-MSS-178 PSA-1/2 B loop room-El.'I3' I
H D
5
- S/G Blowdown 1-WGCB-MSS-18A PSA-1/2 B loop roose-El. 7' I
H D
mS/G Blowdown 1-WGCB-MGS-18B PSA-1/2 B loop room-El. 7' I
H D
5.
O a
l TABLE 4.17-2 UNIT NO. 2 SUPPRESSOR DATA RADIATION REMOVAL SYSTEM DESIGNATION SIZE LOCATION ACCESSIBILITY CATEGORY CATEGORY Charging System 2-CH-HSS-303 1 1/2" Aux. Building A
N R
Charging System 2-CH-HSS-304 1 1/2" Aux. Building A
N R
Charging System 2-CH-HSS-305 1 1/2" Containment Basement I
H R
Charging System 2-CH-HSS-306A 1 1/2" Containment Basement I
H R
Charging System 2-CH-HSS-306B 1 1/2" Containment Basement I
H R
Charging System 2-CH-HSS-307 1 1/2" Cortainment Basement I
H R
Charging System 2-CH-MSS-1 PSA-3 Containment Basement I
H D
Charging System 2-CH-MSS-2 PSA-3 Containment Basement I
H.
D I
Service Water System 2-SW-MSS-1 PSA-3 Containment Basement I
H D
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cu F
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TS 6.4-2 1.
The intent of 10 CFR 20.203(c)(2)(iii) shall be implemented by satisfying the following conditions:
a.
The entrance to each radiation area in which the intensity of radiation is greater than 100 ares /hr but less than 1000 mrea/hr shall be barricaded and conspicuously posted.
b.
The entience to each radiation area in which the intensity of radiation is equal to or greater than 1000 aren/hr shall be provided with locked barricades to prevent unauthorized entry into these areas.
Keys to these locked barricades shall be maintained under the administrative control of the Shif t Supervisor on duty and/or Supervisor Health Physics.
All such accessible high radiation areas shall be surveyed by Health c.
Physics personnel on a routine schedule, as determined by the Supervisor-Health Physics, to assure a safe and practical program.
d.
Any individual entering a high radiation area shall have completed the indoctrination course designed to explain the hazards and safety requirements involved, or shall be escorted at all times by a person who has completed the course.
Any individual or group of individuals permitted to enter a high e.
radiation area per 1.d. above, shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.
Amendment No. 94 and flo. 93
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