ML20056H452
| ML20056H452 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/07/1993 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056H453 | List: |
| References | |
| NUDOCS 9309090352 | |
| Download: ML20056H452 (14) | |
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ylRGINIA 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. 173 License No. NPF-4 1.
The Nucleer Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated July 2,1993, 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.cd safety of the public, and (ii) that such activilies will be conducted in compliance with the Commission's regulations; i
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.
9309090352 930907 PDR ADOCK 05000338 P
l 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 l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.173, 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.
I FOR THE NUCLEAR REGULATORY COMMISSION i
Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical l
Specifications bate of Issuance: September 7, 1993 l
l l
l 1
l
4 ATTACHMENT TO LICENSE AMENDMENT NO. 173 i
TO FACILITY OPERATING LICENSE NO. NPF-4
]
DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with t
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 I
completeness.
Remove Paaes Insert Paaes 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 u
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i 3/4 6 CONTAINMENT SYSTEMS 3/461 CONTAINMENT CONTAINMENTINTEGRITf l
UMITING CONDTDON FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
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APPUCABILITY: MODES 1,2. 3, and 4.
ACTION Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the l
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l SURVElu.ANCE REOUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that all penetrations
- not capable of being closed by OPEF1.GLE containment automatic isolation valves and required to be closed l
during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3.1., and b.
By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.
c.
Aher each closing of the equipment hatch, by leak rate testing the equipment hatch seals with gas at Pa, greater than or equal to 44.1 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Specification 4.6.1.2.b for sti other Type B and C penetrations, the l
combined leakage rate is less than or equal to 0.60 La.
d.
Each time containment integrity is established after vacuum has been broken by
.l pressure testing the butterfly isolation valves in the containment purge lines and the containment vacuum ejector line.
Except valves, blind flanges, and deactivated automatic vafves which are k)cated inside the l
containment and are locked sealed or otherwise sealed in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such' verification need not be performed more often than once per 92 days.
NORTH ANNA-UNIT 1 3/4 6-1 Amendment No. 776, 173 rw
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9 CQtRAltNENT SYSTEMS CCNTA!NMENT EAKAG LIMITING CONDITION FOR OPERATON 3.6.1.2 Containment leakage rates shall be limited to:
l
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a.
An overall integrated leakage rate of less than or equal to La. 0.1 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, at the calculated peak containment pressure Pa.
greater than or equal to 44.1 psig.
b.
A combined leakage rate of less than or equal to 0.60 La for all penetrations and vafves subject to Type B and C tests, when pressurized to Pa, greater than or equal to 44.1 psig.
APPLICABILili MODES 1,2,3, and 4.
l ACTION With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La or (b) with the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 La. restore the overall integrated leakage rate to less than 0.75 La and the combined leakage rate for all penetrations subject to Type B and C tests to less than or equal to 0.60 La Prior to increasing the Reactor Coolant System.'emperature above 200*F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test scheduto l
and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of either ANSI N45.4-1972 for leakage rate point data analysis or ANSI /ANS-56.8-1987 for mass point data analysis with a minimum test duration of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
)
i a.
Type A (Overall Integrated Containment Leakage Rate) tests shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50.
1 i
b.
Type B and C tests shall be conducted with gas at Pa, greater than or equal to 44.1 l
psig, at intervals no greater than 24 months except for tests involving:
1.
Air locks.
l 2.
Penetrations using continuous leakage monitoring systems.
l NORTH ANNA-UNIT 1 3/4 6-2 Amendment No. 7fE, JOB, 770,173
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CONTANAENT SYSTBAS l
COITAMAENT EAKAGF SURVEILLANCE REQUIREMENTS (Conti nued )
c.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement l
4.6.1.3.
d.
Type B tests for penetrations employing a continuous leakage monitoring system shall be conducted at Pa, greater than or equal to 44.1 psig, at intervals no greater than once per 3 years.
e.
All test leakage rates sha!! be calculated using observed data converted to absolute l
5 values. Error analyses shall be performed to select a balanced integrated leakage
{
2 measurement system.
f.
The provisions of Specification 4.0.2 are not applicable.
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NORTH ANNA-UNIT 1 3/4 63 Amendment No. 77p.173
CONTAINMENT SYSTElis i
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_ CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each centain ent air leck shall oe OPEFABLE with:
a.
Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and b.
An overall air lock leakage rate of less than or equal to 0.05 La
.l at Pa greater than or equal to 44.1 psig.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
a.
With one containment air lock door inoperable:
1.
Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed.+
2.
Operation may then continue until performance of the next mquired i
cverall air lock leakage test provided that the OPERABLE air lock coor is verified to be locked, closed at least once per 31 days.
3.
Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the followino 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
4.
The provisions of Specification 3.0.4 are not applicable.
b.
With a containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restort the inoperable air lock to OPEPABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUT-DOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:
'Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following closing, exccot when the air lock is being a.
used for multiple entries, then at least.o.7ce per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying g
that the seal leakage is less than 0.01 La as determined by precision flow measurements when measured for at least 30 seconds with the volume between the seals at a ortssurt of greater than or equal to 44.1 psig..
b.
At least once per 6 months by conducting an overall air lock leakage test at greater than or equal to P, 44.1 psig, and by verifying that l
a the overall air lock leakage rate is within its limitf and
- c..At least once per 18 nonths during shutdown by verifying'that only one door in each air lock can be opened at a time.
+ Entry to repair the inner air lock door, if inoperable, is allowed.
{
- Exempt to Appendix "J" of 10 CFR Part 50.
(The provisions of Specification 4.0.2 are not applicable.
NORTH ANNA - LNIT 1 3/4 6-4 Amenchent No. 75,110 DEC 1 4 I$88 l
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UNITED STATES 0;k'grgfi NUCLEAR REGULATORY COMMISSION
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g wAssincion, o.c. rosss-ooos VIRGINIA ELECTRIC AND POWER COMPANY l
OLD DOMINION ELECTRIC COOPERATIVE i
DOCKET NO. 50-339
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NORTH ANNA POWER STATION. UNIT NO. E l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.154 License No. NPF-7
]
1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated July 2,1993, 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 app'icable requirements have been satisfied.
i
. 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 Operat.ing 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. 154, are hereby incorporated in the license. The licensee shall operate the facility ia 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 NUCLEAR REGULATORY COMMISSION HrbertN.Berkow, Director Project Directorate II-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 7, 1993
k ATTACHMENT TO LICENSE AMENDMENT NO.154 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.
4 The corresponding overleaf pages are also provided to maintain document completeness.
i Remove Paaes Insert Paaes 5
3/4 6-1 3/4 6-1 i
3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 i
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i 3/4.6 CONTAINMENT SYSTEMS l
3/4.6.1 CONTA!NMENT i
CONTAINVENT INTEGRITY I
I UMITING CONDITION FOR OPERATION i
3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
j APPLICABILITY: MODES 1,2,3, and 4.
l l
ACTION:
l t
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the i
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
f t
SURVEILLANCE REOUIREMENTS
\\
4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
I At least once per 31 days by verifying that all penetrations
- not capable of being a.
closed by OPERABLE containment automatic isolation valves and requirsd to be closed during accident conditions are closed by valves, blind flanges, or d) activated r
automatic valves secured in their positions, except as provided in Tabl6 3.6-1 of Specification 3.6.3.1., and b.
By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.
l I
After each closing of the equipment hatch, by leak rate testing the equipment hatch c.
seals with gas at Pa, greater than or equal to 44.1 psig, and verifying that when the j
measured leakage rate for these seats is added to the leakage rates determined pursuant to Specification 4.6.1.2.b for all other Type B and C penetrations, the l
combined leakage rate is less than or equal to 0.60 La.
3 d.
Each time containment integrity is established after vacuum has been broken by pressure testing the butterfly isolation valves in the containment purge lines and the containment vacuum ejector line.
4
- Except valves, blind flanges, and deactivated automatic valves which are located inside the l
containment and are locked sealed or otherwise sealed in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more otten than once per 92 days.
NORTH ANNA-UNIT 2 3/4 6-1 Amendment No. PP.154
i CORA!MAdNT SYSTBAS l
Cor#AINMENT LEAPME i
t UMITING CONDITION FOR OPERATION i
l 3.6.1.2 Containment leakage rates shall be limited to:
An overall integrated leakage rate of loss than or equal to La. 0.1 percent by wehht a.
of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, at the calculated peak containment pressure Pa.
I greater than or equal to 44.1 psig.
t b.
A combined leakage rate of less than or equal to 0.60 La for all penetrations and
~
valves subject to Type B and C tests, when pressurized to Pa. greater than or equal to l
44.1 psig.
I i
APPLICABILITY: MODES 1,2,3, and 4.
l 1
ACTIUt With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La or (b) with the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 La, restore the overall integrated leakage rate to less than 0.75 La I
and the combined leakage rate for all penetrations subject to Type B and C tests to less than or i
equal to 0.60 La prior to increasing the Reactor Coolant System temperature above 200*F.
l SURVEILLANCE REQUIREMETHS l
1 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 l
using the methods and provisions of either ANSI N45.41972 for leakage rate point data analysis or ANSI /ANS 56.8-1987 for mass point data analysis with a minimum test duration j
of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
j a.
Type A (Overall Integrated Containment Leakage Rate) tests shall be conducted in l
accordance with the requirements specified in Appendix J to 10 CFR 50.
b.
Type B and C tests shall be conducted with gas at Pa. greater than or equal to 44.1 l
psig, at intervals no greater than 24 months except for tests involving:
d 3
1.
Air locks.
l t
2.
Penetrations using continuous leakage monitoring systems.
l NORTH ANNA-UNIT 2 3/4 6-2 Amendment No. 77, 7 A, PE.154 i
CCNTANKNT SYST9AS CONTAMENT LEAKAGF i
SURVEll.l.ANCE REOUlREMENTS (Continued) i
-i i
A,r locks shall be tested and demonstrated OPERABLE per Surveillance Requirement l
c.
4.6.1.3.
d.
Type B tests for penetrations employing a continuous leakage monitoring system l
shall be conducted at Pa, greater than or equal to 44.1 psig, at intervals no greater than once per 3 years.
)
e.
All test leakage rates shall be calculated using observed data converted to absolute l
l values. Error analyses shall be performed to select a balanced integrated leakage measurement system.
f.
The provisions of Specification 4.0.E are not applicable.
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NORTP ANNA-UNIT 2 3/4 6-3 Amendment No. PE, 154 l
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+-
Y
CONTAINMENT SYSTEMS i
CONTAINMENT AIR LOCKS LIMITI'NG CONDITION FOR OPERATION f
3.6.1.2 Each containment air lock shall be OPERABLE with:
a.
Both doors closed except when the air lock is being used for normal l
transit entry and exit through the containment, then at least one air lock door shall be closed, and i
b.
An overall air lock leakage rate of less than or equal to 0.05 La at Pa. greater than or equal to 44.1 psig.
l APPLICABILITY: MODES 1, 2, 3 and 4.
i ACTION:
a.
With one containment air lock door inoperable:
j 1.
Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within i
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed.+
2.
Operation may then continue until performance of the next required I
overall air lock leakage test provided that the OPERABLE air lock i
door is verified to be locked closed at least once per 31 day's.
3.
Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
4.
The provisions of Specification 3.0.4 are not applicable.
b.
With a containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1
or be in at least HOT STANDBY within. the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following ?O hours.
SURVEILLANCE REQUIREMENTS 4.5.1.3 Each containment air lock shall be demonstrated OPERABLE:
a.
- Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following closing, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that the seal leakage is less than 0.01 La as detenained by precision flow measurements when measured for at least 30 seconds with the volume between the seals at a pressure of greater than or I
equal to 44.1 psig. -
3
+ Entry to repair the inner air lock door, if inoperable, is allowed.
- Exempt to Appendix "J" of 10 CFR Part 50,,
NORTH ANNA - UNIT 2 3/4 6-4 Amendment No. #1, 96 DEC 141988
.