ML20072J192
| ML20072J192 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/24/1994 |
| From: | Mccree V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072J194 | List: |
| References | |
| NUDOCS 9408260242 | |
| Download: ML20072J192 (22) | |
Text
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t UNITED STATES yg j. f, '.fi[c 7 *j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20 % 0001 i
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C VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.187 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 June 9,1994, complies with tne 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 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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9408260242 940824 PDR ADOCK 05000338 P
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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. 187, 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 CIEAR REGULATORY COMMISSION S
Victor M. McC ee, A ting Director Project Directorat Il-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 24, 1994
ATTACHMENT TO LICENSE AMENDMENT NO.187 TO FACILITY OPERATING LICENSE N0. NPF-4 DOCKET NO. 50-338 1
i 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.
i Remove Pages Insert Paces 3/4 3-1 3/4 3-1 3/4 3-10 3/4 3-10 3/4 3-11 3/4 3-15 3/4 3-15 3/4 3-27 thru 3/4 3-30 3/4 3-27
3L4,3 INSTRUNENTATION 3/4.3.1 REACIOR 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.
l 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 OPERAB&
by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.31.
4.3.1.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactr startup unless performed during the preceedmg 92 days. 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.
4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months. Neutmn detectors are exempt from response time testing. Response of the neutron flux signal portion of the channel time shall be measured fmm the detector output or input of the first electronic component in the channel.
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 every N times 18 months whert 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.
l NORTH ANNA - UNIT 1 3/4 3 1 Amendment No.187
TABLE'3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION HINIMUM E
TOTAL NO.
CilANNELS CHANNELS APPLICABLE
{
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION C
1.
1 2
1, 2 and
- 12 I
2.
Power Range, Meutron Flux 4
2 3
1, 2 2
s 3.
Power Range, Neutron Flux 4
2 3
1, 2 2
High Positive Rate 4.
Power Range, Neutron Flux, 4
2 3
1, 2 2
High Negative Rate 5.
Intermediate Range, Neutron Flux 2
1 2
1, 2 and
- 3 s*
6.
Source Range, Neutron Flux Y
A.
Startup 2
1 2
2,,
4 8.
Shutdown 2
1 2
3*,4* and 5*
15 C.
Shutdown 2
0 1
3, 4 and 5 5
7.
Overtemperature AT Three Loop Operation 3
2 2
1, 2 7f Two Loop Operation 3
1**
2 1, 2 9
E 5
5
4 TABLE 3.3-1 (Continued) ll REACTOR TRIP SYSTEM INTERLOCKS is ALLOWABLE
,g p5SIGNATION CONDITION SETPOINT VALUES FUNCTION 2-P-7 (Cont'd) 3 of 4 Power range below 8%
>7%
Prevents reactor trip when gg setpoint any of the following occur::
and low flow, reactor coolant
-~
((
2 of 2 Turbine Impulse 8%
>7%
pump breakers open, under-chamber pressure below voltage (RCP busses), underi setpoint frequency (RCP busses),
(Power level decreasing) pressurizer low pressure or pressurizer high level.
u>
];
P-8 2 of 4 Power range above 30%
<31%
Allows reactor trip when any of setpoint the following occur: low flow u,
43 in a single loop, a single (Power level increasing) reactor coolant pump breaker open, or a turbine trip.
3 of 4 Power range below 28%
>27%
Prevents reactor trip when setpoint any of the following occur:
low flow in a single loop, (Power level decreasing) a single reactor coolant pump breaker open, or a turbine l[
trip.
a R
A Y.
b
t i
i 1
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i PAGES 3/4 3-10 AND 3/4 3-11 ARE E t.ETED (The next Page is 3/4 3-12) t a
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NORTH ANNA - UNIT I 3/4 3-10 Amendment No. 15, ',i, !!2,187 is....se,
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TABLE 4.3-1 y
REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREFENTS 2
E 5
CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CilECK CAllBRATION TEST REQUIRED e
1.
Manual Reactor Trip N.A.
N.A.
R(7) 1,2 and
- l 2.
Power Range, Neutron Flux 5
D(2),M(3)
M 1, 2 and Q(6) 3.
Power Range, Neutron Flux, N.A.
R(6)
M 1, 2 High Positive P. ate 4.
Power Range, Neutron Flux, N.A.
R(6)
M 1, 2 High Negative Rate S.
Intermediate Range, S
R(6)
S/U(1) 1, 2 and
- y Neutron Flux 6.
Source Range, Neutron Flux N.A.
R(6)
M,S/U(1) 2, 3, 4 and S 7.
Overtemperature ai S
R(6)
M 1, 2 8.
Overpower AT S
R(6)
M 1,.2 3Ig 9.
Pressurizer Pressure--Low S
R M
1, 2 10.
Pressurizer Pressure--High S
R M
1, 2
- 11. itessurizer Water Level--liigh 5
R M
1, 2 12.
Loss of Flow - Single Loop' S
R M
I y
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INSTRUMENTATION 314.3.2 ENGINFFRED SAFETY FEATURE ACTUADON SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION i
3.3.2.1 The Engineemd 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 Serpoint column of Table 3.3-4.
[
APPLICABILITY:
As shown in Table 3.3-3.
ACTION:
With an ESFAS instrumentation channel trip setpoint less conservative than the a.
value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACI' ION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip serpoint adjusted consistent with the Trip Setpoint value, b.
With an ESFAS instrumentation channelinoperable, take the ACTION shown in Table 3.3-3.
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 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 nested 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 the ' Total No. of Channels" Column of Table 3.3-3.
i i
NORTH ANNA - UNIT 1 3/4 3-15 Amendment No. 433,187
~
TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM y.
TOTAL NO.
CHANNELS CHANNELS APPLICABLE 2"
FUNCTIONAL UNIT
'0F CHANNELS TO TRIP OPERABLE MODES ACTION Si 1.
SAFETY INJECTION, TURBINE TRIP AND
- 1 FEEDWATER ISOLATION a.
Manual Initiation 2
1 2
1,2,3,4 18 b.
Automatic Actuation 2
1 2
1,2,3,4 13 c.
Containment 3
2 2
1,2,3,4 14 Pressure-High d.
Pressurizer 3
2 2
1,2,3 14
}{
Pressure-Low-low Y'
e.
Differential 1,2,3 50 Pressure Between Steam Lines -High Three Loops 3/ steam line 2/ steam line 2/ steam line 14 l
Operating twice and 1/3 2
steam lines E
- steam 2/ operating 15 M
Two Loops 3/ operating 2
/
A Operating steam line line twice steam line in either z
P operating steam.line l
El l
f.
Steam Flow in Two 1, 2, 3 c,
j Steam Lines-High I
- ~..
i t
a 4
t PAGES 3/4 3-27 THRU 3/4 3-30 ARE DELETED j
(The next Page is 3/4 3-31) i t
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P P
NORDI ANNA -UNIT 1 3/4 3 2J Amendment No.187 i
+
1 1
~
o otce 2t UNITED STATES y^
NUCLEAR REGULATORY COMMISSION g
g WASHINGTON, 0,C 20555-0001 g
o VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 168 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 June 9,1994, 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 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.
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. 168, 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 liCRQELEAR REGULATORY COMMISSION
/
L Victor M. Mc ree, eting 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: August 24, 1994 l
ATTACHMENT TO LICENSE AMENDMENT NO. 168 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.
Remove Pages Insert Paaes 3/4 3-1 3/4 3-1 3/4 3-10 3/4 3-10 3/4 3-11 3/4 3-15 3/4 3-15 3/4 3-29 thru 3/4 3-32 3/4 3-29
3L42 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.
l APPLICABILITY:
As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVEILLANCE REQUIREMENTS r
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 FUNCIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.
4.3.1.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactor stanup unless performed during the preMag 92 days. 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.
4.3.1.1.3 The REAGOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months. Neutron detectors are exempt from response time testing. Response of the neutron flux signal ponion of the channel time shall be measured from the detector output orinput of the first electronic component in the channel.
Each test shallinclude 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 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.
l NORTH ANNA - UNIT 2 3/43-1 Amendment No.168
TABLE 3.3-1 REACTORTRIPSYSTEMINSTRUMENTATIbN m
E 58 h
2" MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CllANNELS TO TRIP OPERABLE MODES ACTION E
Z 1.
1 2
1, 2 and
- 12 to 2.
Power Range, Neutron Flux 4
2 3
1, 2 2#
3.
Power Range, Neutron Flux 4
2 3
1, 2 2f High Positive Rate
'4 4
Power Range, Neutron Flux 2
3 1, 2 2f High Megative Rate
{
5 Intermediate Range, Neutron Flux 2
1 2
1, 2 and
- 3 Y
6 Source Range, Neutron Flux
- t@
A.
Startup 2
1 2
2ff 4
B.
Shutdown 2
1 2
3*, 4* and 5*
15 C.
Shutdown 2
0 1
3, 4 and 5 5
7 Overtemperature aT
{
Three loop Operation 3
2 2
1, 2 7f g
Two Loop Operation 3
1**
2 1, 2 9
R
?.
g 3
.ms J
TABLE 3.3-1 (Continued) z REACTOR TRIP SYSTEM INTERLOCKS ALLOWABLE DESIGNATION CONDITION SETPOINT VALUES
[
P-7 (Cont'd) 3 of 4 Power range below 8%
>7%
Prevents reactor trip when any
' gg setpoint of the following occur: low
-d and flow, reactor coolant pump 2 of 2 Turbine Impulse 8%
>7%
breakers open, undervoltage chamber pressure below (RCP busses), underfrequency setpoint (RCP busses), pressurizer (Power level decreasing) low pressure or pressurizer high level.
P-8 2 of 4 Power range above.
30%
<31%
Allows reactor trip wh'en any setpoint of the following occur: low flow in a single loop, a single (Power level increasing) reactor coolant pump breaker R',
open, or a turbine trip.'
s
't*
3 of 4 Power range below 28%
>27%
Prevents reactor trip when any setpoint of the following occur:
low us flow in a single loop, a single (Power level decreasing) reactor coolant pump breaker open, or a turbine trip.
E ait an a
to
m.
l' PAGES 3/4 310 AND 3/4 3-11 ARE DELETED (The next Page is 3/4 3-12) 1 NORTH ANNA - UNIT 2 3/4 3-10 Amendment No. ?!, ie,3 :5, 443,168
ij TABLE _4.3-1 4
[
REACTOR TRIP SYSTEN INSTRUMENTATION SURVEILLANCE REQUIREMENTS 55 CHANNEL MODES IN MilCil e
c:
CilANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT Cll[CK CAllBRATION TEST REQUIRE 0 1.
Manual Reactor Trip H.A.
N.A.
R(8) 1,2 and
- 2.
Power Range, Neutron Flux 5
D(2), M(3)
M 1, 2 and Q(6) 3.
Power Range, Neutron Flux, M.A.
R(6)
M 1, 2 High Positive Rate
,s 4.
Power Range, Neutron Flux, N.A.
R(6)
M 1, 2
[
High Negative Rate m
5.
Intermediate Range, S
R(6)
S/U(1) 1, 2, and
- Neutron Flux 6.
Source Range, Neutron Flux S(7)
R(6)
M S/U(1) 2, 3, 4, 5, and
- 7.
Overtemperature AT S
R(6)
M 1, 2 8.
Overpower AT S
R(6)
M 1, 2
{
9.
Pressurizer Pressure--Low S
R M
1, 2 3
5 10.. Pressurizer Pressure--High 5
R M
1, 2 11.
Pressurizer Water level--High 5
R M
1, 2 12.
Loss of Flow - $1ngle Loop
'S R
M 1
~,
INSTRUMENTATION 3/4.3.2 ENGINFFRFn SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION l
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 ut consistent with the values shown in the Trip Setpoint column of Table 3.3-4 APPLICABILITY:
As shown in Table 3.3-3.
ACTION:
With an ESFAS instrumentation channel trip serpoint less conservative than the a.
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 serpoint adjusted consistent with the Trip Setpoint value.
b.
With an ESFAS instrumentation channelinoperable, take the ACTION shown in Table 3.3-3.
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
.j 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. 'Ihe 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 SAFE 1Y 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 j
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 the ' Total No. of Channels" Column of Table 3.3-3.
NORTH ANNA - UNIT 2 3/4 3-15 Amendment No. 4GE.168 i
L
TABLE 3.3-3 2c>
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 2
MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION E
- 1 1.
SAFETY INJECTION, TURBINE TRIP AND FEkDWATERISOLATION s,
a.
Manual Initiation 2
1 2
1,2,3,4 18 b.
Automatic Actuation 2
1 2
1,2,3,4 13 a
c.
Containment 3
2 2
1,2,3,4 14 Pressure-High d.
Pressurizer 3
2 2
1, 2, 3 14 Pressure --
Low-Low u,
5 e.
Differential 1,2,3 u,
2, Pressure Between Steam Lines - High o'
n Three Loops 3/ steam line 2/ steam line 2/ steam line 14 Operating twice and 1/3 steam lines Two Loops 3/ operating 2
/ steam 2/ operating 15 Operating steam line line twice steam line E
in either operating it steam line e
r+
PAGES 3/4 3-29 THRU 3/4 3-32 ARE DELETED (The next Page is 3/4 3-33) l l
NORTH ANNA - UNIT 2 3/4 3-29 Amendment No.168