ML20137U400
| ML20137U400 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/21/1985 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137U404 | List: |
| References | |
| NUDOCS 8512090292 | |
| Download: ML20137U400 (12) | |
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NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
'+,.....,o VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINTON ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 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 September 24, 1985, 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; 1
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 activitics authorized I
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 Comission's regulations; j
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.
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B51'2090292 851121 PDR ADOCK 05000338 i
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, 2.
Accordingly, the license is amended by changes to the Technical Spect-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 8, as revised through Amendment No. 72, 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 h
)
Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 21, 1985 i
ATTACHMENT TO LICENSE AMENDMENT NO. 72 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.
Remove Pages Insert Pages 3/4 7-29 3/4 7-29 3/4 7-30 3/4 7-30
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
The snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
b.
Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visual indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly estab-lished and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specifications 4.7.10.d and 4.7.10.e.
When hydraulic snubbers which have uncovered fluid ports.are tested for operability, the tests shall_be performed by starting with the piston at the as-found setting and extend-ing the piston rod in the tension mode direction. Snubbers whien have been determined to be inoperable as a result of unexpected transients, isolated damage, or other random events, and cannot be proven operable by functional testing for the same reasons, shall not be counted in deter-mining the next visual inspection period when the provision in 4.7.10.c that failures are subject to an engineering evaluation of component structural integrity has been met and equipment has been restored to an operable state via repair and/or replacement as necessary.
c.
Functional Tests At least once per 18 months during shutdown, a representa ive sample of small bore snubbers which follows the expression 35 [1 +
, where c=2 is the allowable number of small bore snubbers not meetin the acceptance criteria selected by the operator, shall be functionally tested either in-place or in a bench test. For each number of small bore snubbers above c which does not meet the functional test acceptance criteria of Specification 4.7.10.d or 4.7.10.e. an additional sample seMcted accord-ing to the expression 35(1+{}(c (a - c) 1 shall be functionally tested, where a is the total number of small bore l
snubbers found inoperable during the functional testing of the represent-ative sample.
Functional testing shall continue according to the expression b[35(1+{}(c 1 ) ] where b is the number of snubbers found inoper-able in the previous re-sample, until no additional inoperable snubbers are found within a sample or until all small bore snubbers have been functionally tested.
l NORTH ANNA - UNIT 1 3/4 7-29 Amendment No. 33,71, 72
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
At least once per 18 months during shutdown,10% of the large bore i
snubbers (snubbers greater than 50 kips) shall be functionally tested l
either in place, in a full snubber bench test, or in a snubber valve j
block bench test. For each large bore snubber that does not meet the i
functional test acceptance criteria of Specification 4.7.10.d, an j
engineering evaluation is required to determine the failure mode.
If the failure is detennined to be generic, an additional 10% of that type 1
of snubber shall be functionally tested.
If the failure is determined l
I to be non-generic, an additional 10% of that type of snubber will be tested during the next functional test period.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. At least 25% of the snubbers in the represent-ative sample shall include snubbers from the following three categories:
1.
The first snubber away from each reactor vessel nozzle.
2.
Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor,etc.).
i 3.
Snubbers within 10 feet of the discharge from a safety relief i
valve.
i Snubbers that are "Especially Difficult to Remove" or in "High Radia-tion Zones During Shutdown" shall also be included in the representative
{
}
samples.* Accessible and inaccessible snubbers may be used jointly or j
separately as the basis for the sampling plan.
f In addition to the regular sample, snubbers which failed the previous j
functional test shall be retested during the next test period.
If a i
spare snubber has been installed in place of a failed snubber, then both j
the failed snubber (if it is repaired and installed in another position) l i
and the spare snubber shall be retested. Test results of these snubbers j
j may not be included for the re-sampling.
i If any snubber selected for functional testing either fails to lockup l
or fails to move, i.e., frozen in place, the cause will be evaluated and
{
if caused by manufacturer or design deficiency all snubbers of the same l
j design subject to the same defect shall be functionally tested. This j
testing requirement shall be independent of the requirements stated above t
for snubbers not meeting the functional test acceptance criteria.
I
- Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Comission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all= design conditions at either j
the completion of their fabrication or at a subsequent date.
l l
NORTH ANNA - UNIT 1 3/4 7-30 Amendment No. 33, M,71, 72
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y'o,j UNITED STATES NUCLEAR REGULATORY COMMISSION y
,t WASHINGTON, D. C. 20555
/
VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.58 License No. NPF-7 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 September 24, 1985, complies with the standards and requirement: of the Atomic Energy Act of 1954, as amended (the Act), and the Comistion'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; 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.
. 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. 58, 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 Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 21, 1985 t
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i ATTACHMENT TO LICENSE AMENDMENT NO. 58 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 Pages 3/4 7-26 3/4 7-26 3/4 7-27 3/4 7-27 T,
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PLANT SYSTEMS 3/4.7.10 SNUBBERS LIMITING CONDITION FOR OPERATION i
3.7.10 All snubbers utilized on safety related systems shall be OPERABLE.
For those snubbers utilized on non-safety related systems, each snubber shall be OPERABLE if a failure of that snubber or the failure of the non-safety related i
system would have an adverse effect on any safety related system.
j i
APPLICABILITY: MODES !, 2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems required OPERABl.E in those MODES).
t ACTION:
i i
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the j
inoperable snubber (s) to OPERABLE status and perform an engineering evaluation t
per Specification 4.7.10.c on the supported component or declare the supported l
system inoperable'and follow the appropriate ACTION statement for that system.
f SURVEILLANCE REQUIREMENTS 1
4.7.10 Each snubber shall be demonstrated OPERABLE by performance of the I
following augmented inservice inspection program and the requirements of f
Specification 4.0.5.
[
a.
Visual Inspections
\\
The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of commencing POWER OPERATION j
and shall include the snubbers defined in 3.7.10.
If less than two (2) l snubbers are found inoperable during the first inservice visual inspec-
[
tion, the second inservice visual inspection shall be performed 12
{
months + 25% from the date of the first inspection. Otherwise, subse-6 quent vTsual inspections shall be performed in accordance with the i
following schedule:
)
No. Inoperable Snubbers Subsequent Visual
[
per Inspection Period Ins)ection Period *f j
0 15 months + 25%
1 12 months T 25%
2 6 months T 25%
3, 4 124 days + 25%
5,6,7 62 days T 25%
J a
8 or more 31 days T 25%
Early inspections (i.e. those performed before 75% of the current i-inspection period has elapsed) may be used to set new reference surveil-lance dates for the current inspection period. However, the results of 3
such early inspections cannot be used to increase the current inspection
[
period (period may only stay the same or decrease as determined by the tablein4.7.10.a).
l
- The inspection interval shall not be lengthened more than one. step at a time.
f
- The provisions of Specification 4.0.2 are not applicable.
NORTH ANNA - UNIT 2 3/4 7-25 Amendment No. J3, 57
)
1 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
The snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor operation.
Each group may be inspected l
independently in accordance with the above schedule.
b.
Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visual indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection i
interval, providing that (1) the cause of the rejection is clearly estab-lished and remedied for that particular snubber and for other snubbers t
that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and deterinined OPERABLE per Specifications 4.7.10.d and 4.7.10.e.
When hydraulic snubbers which have uncovered fluid ports are tested for operability, the tests shall be per-formed by starting with the piston at the as-found setting and extending the piston rod in the tension mode direction. Snubbers which have been determined to be inoperable as a result of unexpected transients, isolated damage, or other random events, and cannot be proven operable by func-l tional testing for the same reasons, shall not be counted in determining
~
the next visual inspection period when the provision in 4.7.10.c that failures are subject to an engineering evaluation of component structural integrity has been met and equipment'has been restored to an operable j
state via repair and/or replacement as necessary.
i c.
Functional Tests l
At least once per 18 months during shutdown, a representa ive sample of small bore snubbers which follows the expression 35 [1 +
, where c=2 i
is the allowable number of small bore snubbers not meetin the acceptance criteria selected by the operator, shall be functionally tested either in-place or in a bench test. For each number of small bore snubbers above c which does not meet the functional test acceptance criteria for 1
Specification 4.7.10.d or 4.7.10.e an additional sample selected l
~
according to the expression-35(1+j)(
)2(a-c) 2
]
shall be functionally tested, wher'e a is the total number of small bore snubbers found inoperable'during the functional testing of the represent-j ative sample.
l.
Functional testing shall continue according to the expression f
b [ 35 (1 + c) { c 1 ) ] where b is the number of snubbers found inoper-g l
able in the previous re-sample, until no additional inoperable snubbers are found within a sample or until all small bore snubbers have been functionally tested.
l NORTH ANNA - UNIT 2 3/4 7-26 Amendment No. J3,57,58
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
At least once per 18 months during shutdown,10% of the large bore snubbers (snubbers greater than 50 kips) shall be functionally tested either in place, in a full snubber bench test, or in a snubber valve block bench test.
For each large bore snubber that does not meet the functional test acceptance criteria of Specification 4.7.10.d, an engi-neering evaluation is required to determine the failure mode.
If the failure is determined to be generic, an additional 10% of that type of snubber shall be functionally tested.
If the failure is determined to be non-generic, an additional 10% of that type of snubber will be tested during the next functional test period.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. At least 25% of the snubbers in the represen-tative sample shall include snubbers from the following three categories:
1.
The first snubber away from each reactor vessel nozzle.
2.
Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor,etc.).
4 3.
Snubbers within 10 feet of the discharge from a safety relief valve.
i t
Snubbers that are "Especially Difficult to Remove" or in "High Radia-tion Zones During Shutdown" shall also be included in the representa-tive samples.* Accessible and inaccessible snubbers may be used jointly or separately as the basis for the sampling plan.
[
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.
If a spare snubber has been installed in place of a failed snubber, then
[
both the failed snubber (if it is repaired and installed in another
~
position) and the spare snubber shall be retested. Test results of these snubbers may not be included in the re-sampling.
If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same i
design subject to the same defect shall be functionally tested. This l
testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
- Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable l'
basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
NORTH ANNA - UNIT 2 3/4 7-27 Amendment No. J3, M,57, 58
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
For the snubber (s) found inoperable, an engineering' evaluation shall be performed on the components which are supported by the snubber (s).
The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the design service.
d.
Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:
1.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
2.
Snubber bleed, or release rate, where required, is within the specified range in compression or tension. For snubbers specif-ically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
e.
Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
1.
The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force. Drag force shall not have increased more than 50%
since the last functional test.
1 2.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compres-sion.
3.
Snubber release rate, where required, is within the specified range in compression or tension. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
f.
Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be main-tained as required by Specification 6.10.2.
NORTH ANNA - UNIT 2 3/4 7-28 Amendment No. J3, 24, 57 l
..