ML20206F005
| ML20206F005 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/10/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206F009 | List: |
| References | |
| NUDOCS 8606240091 | |
| Download: ML20206F005 (7) | |
Text
ff asog$o pa UNITED STATES 3 g NUCLEAR REGULATORY COMMISSION y
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j WASHINGTON, D. C. 20555 3
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f VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. NPF-4 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated February 5, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as
}
amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l ION 00$ BIO je P
. 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.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 82, 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 f
ester S. Rubenstein, Director l
PWR Project Directorate #2 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: June 10,1986 i
i f
1
ATTACHMENT TO LICENSE AMENDMENT NO. 82 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
3/4 3-2 3/4 3-3
i 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.
APPLICABILITY: As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and l
at the frequencies shown in Table 4.3-1.
4 4.3.1.1.2 The logic for the interlocks shall be demonstrated OPERABLE l
prior to each reactor startup unless performed during the preceeding 92 days. The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each I
channel affected by interlock operation.
~
4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per l
18 months. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel' J
l per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3.1.
I j
NORTH ANNA - UNIT 1 3/4 3-1
I TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION HINIMUM E
TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE _
MODES ACTION E
1.
1 2
1, 2 and
- 12 2.
Power Range, Neutron Flux 4
2 3
1, 2 2
3.
Power Range, Neutron Flux 4
2 3
i, 2 2
High Positive Rate 4.
' Power Range, Neutron Flux, 4
2 3
'.2 2
- High Negative Rate 5.
Intermediate Range, Neutron Flux 2
1 2
1, 2 and
- 3 6.
Source Range, Neutron Flux Y
A.
Startup 2
1 2
2,, and
- 4 B.
Shutdown 2
0 1
3, 4 and 5 5
7.
Overtemperature AT Three Loop Operation 3
2 2
1, 2 7,
l l
Two Loop Operation 3
1**
2 1, 2 9
E a
ili E
5 e
e
i
(
l TABLE 3.3-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION 5:
MINIMUM 3;
TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION b
8.
Overpower AT i'i Three Loop Operation 3
2 2
1, 2 7,
l
]
Two Loop Operation 3
1**
2 1, 2 9
9.
Pressurizer Pressure-Low 3
2 2
1, 2 7
- 10. Pressurizer Pressure--High 3
2 2
1, 2 7
- 11. Pressurizer Water Level--High 3
2 2
1, 2 7
- 12. Loss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in 1
7 (Above P-8) any oper-each oper-w2 ating loop ating loop
- 13. Loss of Flow - Two Loops 3/ loop 2/ loop in 2/ loop 1
7 (Above P-7 and below P-8) two oper-each oper-ating loops ating loop
- 14. Steam Generator Water 3/ loop 2/ loop in 2/ loop in 1, 2 7
Level--Low-Low any oper-each oper-g ating loops ating loop (D
h
- 15. Steam /Feedwater Flow 2/ loop-level 1/ loop-level 1/ loop 1, 2 7
g Mismatch and Low Steam and coincident level and Generator Water Level 2/ loop-flow with 2/ loop-flow g
mismatch 1/ loop-flow mismatch or mismatch in 2/1 cop-level same loop and co 1/ loop-flow mismatch i
I TABLE 3.3-1 (Continu:d)
- REACTOR TRIP SYSTEM INSTRUMENTATION Ei MINIMUM fl TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION ii
- 16. Undervol tage-Reactor 3-1/ bus 2
2 1
7#
Coolant Pump Busses e
C
'5
- 17. Underfrequency-Reactor 3-1/ bus 2
2 1
7#
((
Coolant Pump Busses
- 18. Turbine Trip A.
Low Auto Stop Oil Pressure 3
2 2
1 7#
B.
Turbine Stop Valve Closure 4
4 4
1 7f
- 19. Safety Injection Input from ESF 2
1 2
1,2 1
us
- 20. Reactor Coolant Pump Breaker 3
Position Trip us A.
Above P-8 1/ breaker 1
1/ breaker 1
10 I-B.
Above P-7 1/ breaker 2
1/ breaker 1
11 per operating loop 21.
A.
Reactor Trip Breakers 2
1 2
1,2 1,14 2
1 2
3*,4*,5*
15 B.
Reactor Trip Bypass Breakers 2
1 2
13 2
1 2
1,2 1
- 22. Automatic Trip Logic 2
1 2
3*,4*,5*
15 co 2
a
.E 9
9 9
Y
.