ML20247C735
| ML20247C735 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/07/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247C740 | List: |
| References | |
| NUDOCS 8909140093 | |
| Download: ML20247C735 (17) | |
Text
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UNITED STATES 3
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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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
~~
Amendnent No.123 License No. NPF-4 1.
The Nuclear Regulatory Connission (the Connission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated July 12, 1989, as supplemented l.
July 26,1989, complies with the standards and requirements of the i
Atomic Energy Act of 1954, as amended (the Act), and the Commission's f
rules and regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Connission; 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 l
conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the connon l
defense and security or to the health and safety of the public; I
and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Connission'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 '11 cense 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, f
as revised through Amendment No. I23, 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 T-5.c.B"ck Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 7, 1989 4
i 1
ATTACHMENT TO LICENSE AMENDMENT NO. 12s 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 nunber and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
-,l Page 3/4 3-15 3/4 3-31 3/4 3-32 1
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,3/4 3-33 1
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INSTRLSIENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION
-i LIMITING CONDITION FOR OPERATION
~3.3 2.1 The
-Engineered Safety Feature Actuation System (ESFAS)~
instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with. their. trip setpoints set, consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown' in Table 3.3-5.
-APPLICA8ILITY: As shown in Table 3.3-3.
ACTION:
a.
With ~an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4',
declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With an ESFAS. instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.-
SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE
.1 by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION, CHANNEL FUNCTIONAL. TEST. and SLAVE RELAY TEST operations for the MODES and at the frequencies shown in Table 4.3-2.
4.3.2.1.2 The logic for the. interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.
The total interlock function shall be demonstrated OPERABLE at least once per 18 months during, CHANNEL CALIBRATION testing of each channel affected by interlock operation.
4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 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 per function such that
'all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in e
the " Total No. of Channels" Column of Table 3.3-3.
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TABLE NOTATION 3
(1)' Manual actuation switches shall be tested at least once per 18 months j
during shutdown.
(2) Each train or logic channel shall be functionally tested at least every other 31 days up to and including input coil continuity testing to the ESF slave relays.
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-(3) The CHANNEL FUNCTIONAL TEST shall include exercising the tra'nsmitter by applying either a vacuum or pressure to the appropriate side of the transmitter.
(4) Only slave relays that do not satisfy any of, the following criteria will be functionally tested:
- 1.. A single failure in the Safeguards Test Cabinet circuitry would cause j
an inadvertent RPS or ESF actuation.
J 2.
The. test will adversely affect two or.more components in one ESF system or two or more ESF systems.
3.
The test will create a transient -(reactivity, thermal, or hydraulic) condftion on the RCS.
NORTH ANNA - UNIT 1 3/4 3-34 Amendment No. 123 i
f.
4'o UNITED STATES e-NUCLEAR REGULATORY COMMISSION o
,b.
WASHINGTON, D. C. 20555
%...../
y VIRGINIA ELECTRIC AND POWER COMPANY i
OLD DOMINION ELECTRIC COOPERATIVE
. DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2
~
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 107 License No. NPF-7 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Co gany-et al., (the licensee) dated July 12, 1989, as supplemented July 26,1989, 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 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; i
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 Commission's regulations and all applicable requirements have been satisfied.
4
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t 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendnent, i
and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby 1
amended.to read as follows:
(2) Technical Specifications i
i The Technical Specifications contained in Appendices. A and B, j
as revised through Amendment No. 107
, 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.
j
.3 FOR THE NUCLEAR REGULATORY COMMISSION i
i 3 c.haiu 17 Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical
)
Specifications j
i Date of Issuance:
September 7, 1989 i
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ATTACHMENT TO LICENSE AMENDMEN1 NO. in7 l-I' TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 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 3-15 3/4 3-33 3/4.3-34 3/4 3-35 3/4 3-36 3/4 3-37 1'
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INSTRUMENTATION i
3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The-Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall beOPERABLE with their trip setpoints set Setpoint column of Table 3.3-4 and consistent with the values shown in the Trip with RESPONSE TIMES as shown in Table 3.3-5.
APPLICABILITY: As shown in Table 3.3-3.
i ACTION:
l a.
With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.
1 b.
With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.
l SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION, CHANNEL
{
FUNCTIONAL TEST and SLAVE RELAY TEST operations for the MODES and at the l
frequencies shown in Table 4.3-2.
4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during i
the automatic actuation logic test.
The total interlock function shall be
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demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.
4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 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 per function such that dll Channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.
i NORTH ANNA - UNIT 2 3/4 3-15 Amendment No. 107
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l N N - WIT 2 3/4 3-36 Amendment No. 107 n
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TABLE 4.3-2 (Continued)
(
TABLE NOTATION (1)' Manual actuation switches shall be tested at least once per 18 months during~ shutdown.
(2) Each train or logic channel shall be functionally tested at least every i
other 31 days up to and including input coil continuity testing to the ESF slave relays.
(3) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of. the transmitter.
(4)
Only slave relays that
' be functionally tested: g not satisfy any of the following criteria will 1.
A single failure in the Safeguards Test Cabinet circuitry would cause an inadvertent RPS or ESF actuation.
2.
The test will adversely affect two or more components in one ESF system or two or more ESF systems.
3.
The test will create a transient (reactivity, thermal, or hydraulic) condition on the RCS.
l l
l NORTH ANNA - UNIT 2 3/4 3-37 Amendment No. 107
-- J