ML20056A578
| ML20056A578 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/31/1990 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056A579 | List: |
| References | |
| NUDOCS 9008080266 | |
| Download: ML20056A578 (9) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.133 License No. NPF-4 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated May 16, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Cor., mission'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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.
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2 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in tne attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby r
amended to read as follows:
(2) Technical Specifications l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.133, 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 issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION erbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 31,1990 f
f i
t ATTACHMENT TO LICENSE AMEN 0 MENT NO.133 t
TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 l
Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment number and contains vertical lines indicating the area of change.
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y TABLE 3.3-6 (continue (')
g RADIATION MONITORING INSTRUNENTATION E
U CtW#ELS APPUCABLE ALARM / TRIP MEASURDAENT INSTRUMENT OPERABLE MODES SETPOINT RANGE
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- 2. PROCESSMONITORS(Contd)
- c. Noble Gas High Range Effluent Monitors i.
Ventilation Vent #
1 1.2.3. & 4 Hi 54.72x10 pCi/sec 5 x 10 10 + 5pCi/cc 35 6
7 Hi Hi 51.89x10 pCi/sec 6'
ii. Process Vent #
1 1.2.3. & 4 Hi 54.72x10 pCi/sec 5 x 10 10 + 5pCi/cc 35 7
Hi Hi s1.89x10 pCi/sec u
Y iii. Main Steam ##
1/ loop 12.3. & 4 Hi $1.0 mR/hr 10-2.1 o + 7 mR/hr 35 Hi Hi 54.0 mR/hr o
iv. Auxiliary Feedwater Pump Turbine Exhaust 1
1.2.3, & 4 Hi 50.7 mR/hr 10 -2.10 + 7 mR/hr 35 Hi Hi 52.8 mR/hr N
R Common to Unit 1 and Unit 2.
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- Main steam release path includes safety valves, atmospheric steam dump valve, and the decay heat release path.
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VIRGINIA ELECTRIC AND POWER COMPANY l
OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.117 License No. NPF-7 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated May 16, 1990, complies with the standards and requirrments 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 (1) 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; 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 Commission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B.
as revised through Amendment No. 117 are hereby incorporated in the license.
The licensee shall ope, rate the facility in accordonce with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION i
He ert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July ?l, 1990 t
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.j ATTACHMENT TO LICENSE AMENDMENT NO.117 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 r.
Replace the following page of the Appendix "A" Technical Specifications e
with the enclosed page as indicated.
The revised page is identified by amendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
P,agg 3/4 3-39a e
1
ne' TABLE 3.3-6 h
RADIATION MONITORING INSTRUMENTATION G
t MINIMUM i
32 CilANNELS APPLICARLE ALARM / TRIP MEASUREMENT 7
INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION
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AREA MONITORS w
m a.
Fuel storage Pool Area
< 15 mR/hr 10-# - 10 R/hr 22 Criticality Monitor i I
b.
Containment 1.
Purge & Exhaust
- 10,f R/hr
-4 Isolation 1
6
< 50 mR/h 10 25
- 11. High Range Area 2
1,2,3, & 4 51.6x10+gR/hr 0
- 10+
10 R/hr 35 l
-t' 2.
PROCESS MONITORS Y'g a.
Ventilation Vent #
- i. Gaseous Gross
< 1 x 10-5 pC1/mi 10 - 10 cpm 24 6
Activity 1
- 11. Particulate Gross i
6
< 2 x 10-9 uCi/ml 10 - 10 cpm 24 Activity 1
b.
Containment 1.
Gaseous Activity a) Purge & Exhaust 3
6 Isolation 1
6
< 3.6 x 10 cpm 10 - 10 cpm 25 b) RCS Leakage 6
Detection 1
1,2,3, & 4 N/A 10 - 10 cpm 23 ii. Particulate Activity a) Purge & Exhaust 6
Ise4ation 1
6 b) ku Leakage
-< 1 x 10 cpm 10 - 10 cpm 25 6
Detection 1
1,2,3, & 4 N/A 10 - 10 cpm.
23
- With fuel in the storage pool or building
- With irradiated fuel in the storage pool f Common to Unit I and Unit 2
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5 x2 TABLE 3.3-6 (continued) f 88Dl!@GUd2flOSNG N E
CHMeELS APPUCABLE ALARM / TRIP REASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION
- 2. PROCESSMONITORS(Conrc$
- c. Noble Gas High Range I
Effluent Monitors 1.
Ver.lilation Vent #
1 1.2.3, 8 4 Hi s4.72x10 pCi/sec S x 10 10 + 5pCl/cc 35 6
i 7
Hi Hi 51.89x10 pCl/sec t
j li. Process Vent #
1 1.2.3. 8 4 Hi 54.72x10 pCi/sec 5 x 10 10 + 5pCl/cc 35 6
7 Hi Hi s1.89x10 pCi/sec M
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iii. Main Steam ##
1/ loop 1,2,3, & 4 Hi s1.0 mR/hr 10-2.10 + 7 mR/hr 35 4
Hi Hi 54.0 mR/hr
'o, iv. Auxiliary Feedwater i
Pump Turbone Exhaust 1
1,2 2, & 4 Hi 50.7 mR/hr 10 10 + 7 mR/hr 35 Hi Hi 52.8 mR/hr l
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e i
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Common to Unit 1 and Unit 2.
y Main steam release path includes safety valves, almospheric steam dump valves and the decay heat release path.
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