ML20137T898
| ML20137T898 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/20/1985 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137T902 | List: |
| References | |
| GL-84-13, NUDOCS 8512090153 | |
| Download: ML20137T898 (27) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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WASMNGTON, D. C 20555
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VIPGINTA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRTC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 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 19, 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; 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 (1) 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.
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s 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 Spec fications contained in Appendices A and B, as revised through Amendment No. 71, 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:
1 Changes to the Technical l
Specifications Date of Issuance:
November 20, 1985 9
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ATTACHMENT TO LICENSE AMENDMENT NO. 71 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclcsed 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 7-28 3/4 7-28 3/4 7-29 3/4 7-29 3/4 7-29a 3/4 7-30 3/4 7-29b 3/4 7-31 3/4 7-29c 3/4 7-32 3/4 7-30 thru 3/4 7-67 3/4 7-67 8 3/4 7-6 B 3/4 7-6 6-23 6-23
e e
e PLANT SYSTEMS RHR - SHUTDOWN LIMITING CONDITION FOR OPERATION As a minimum, one residual heat removal subsystem shall be 3.7.9.2 OPERABLE.
APPLICABILITY: MODES 4 and 5.
ACTION:
With no Residual Heat Removal subsystem OPERABLE, immediately restore at least one RHR subsystem to OPERABLE status or maintain the Reactor less than 350.F by use of alternate heat removal l
Coolant System T methods. The pr859sions of Specifications 3.0.3, 3.0.4 and 4.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS Each Residual Heat Removal subsystem shall be demonstrated 4.7.9.2 OPERABLE per the applicable Surveillance Requirement of Specification 4.7.9.1, and At least once per 31 days by; a.
Cycling each testable, remote or automatically operated 1.
valve through at least one complete cycle, and Verifying the correct position of each manual valve not
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locked sealed or otherwise secured in position, and Verifying the correct position of each remote or auto-3.
matica11y operated valve.
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Amendment No. 3 NORTH ANNA - UNIT 1 3/4 7-27 2
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PLANT SYSTEMS 3/4.7.10 SNUBBERS LIMITING CONDITION FOR OPERATION 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 system would have an adverse effect on any safety related system.
APPLICABILITY: MODES 1, 2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
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 inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.10.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.10 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of 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 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-quent vTsual inspections shall be performed in accordance with the following schedule:
i No. Inoperable Snubbers Subsequent Visual per Inspection Period Ins)ection Period *#
0 13 months + 25%
1 12 months T 25%
2 6 months T 25%
3, 4 124 days + 75%
5,6,7 62 days T 25%
8 or more 31 days _T 25%
Early inspections (i.e., those perforined before 75% of the current inspec-tion period has elapsed) may be used to set new reference surveillance dates for the current inspection period. However, the results of such early in-1 spections cannot be used to increase the current inspection period (period may only stay the same or decrease as determined by the table in 4.7.10.a).
- The inspection interval shall not be lengthened more than one step at a time.
- The provisions of Specification 4.0.2 are not applicable.
NORTH ANNA - UNIT 1 3/4 7-28 Amendment No. 33,71
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 detennined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established 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.
However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be detennined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval. All snubbers connected to an inoperable comon hydraulic fluid reservoir shall be counted as inoperable snubbers.
c.
Functional Tests At least once per 18 months during shutdown, a representative sap of that number of snubbers which follows the expression 35 [1 +
where c=2 is the allowable number of snubbers not meeting the ac} cept-ance criteria selected by the operator, shall be functionally tested either in-place or in a bench test. For each number of 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 selected according to the expression 35(1+{)(c 1)
(a - c) shall be functionally tested, where a is the total number of snubbers found inoperable during the functional testing of the representative sample.
Functional testing shall continue according to the expression b[35(1+y)(c 1 ) ] where b is the number of snubbers found l
inoperable in the previous re-sample, until no additional inoperable snubbers are found within a sample or until all snubbers have been functionally tested.
j NORTH ANNA - UNIT 1 3/4 7-29 Amendment No. 33,71
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
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 representative sample shall include snubbers from the following three categories:
1.
The first snubber away from each reacter vessel nozzle 2.
Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor,etc.).
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Snubbers within 10 feet of the discharge from a safety relief valve.
Snubbers that are "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative 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 for 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 design subject to the same defect shall be funct hnally t
tested. This testing requirement shall be independent of the require-ments stated above for snubbers not meeting the functional test acceptance criteria.
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- Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Connission 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 the completion of their fabrication or at a subsequent date.
t NORTH ANNA - UNIT 1 3/4 7-30 Amendment No. 33, M, 71, l
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
For the snubber (s) found inoperable, an engineering evaluation shall be perforined 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 specifically required to not displace under continuous load, the ability of the snubber to withstand load without displace-ment 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.
2.
Activation (restraining action) is achieved within the specifit.d range of velocity or acceleration in both tension and compression.
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 1
verified.
f.
Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life comences 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.
l NORTH ANNA - UNIT 1 3/4 7-31 Amendment No. 33, M,71
I PLANT SYSTEMS
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SURVEILLANCE REQUIREMENTS (Continued)
L At least once per 18 months, the installation and maintenance records l
for each snubber defined in 3.7.10 shall be reviewed to verify that i
the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.
If the indicated service life will be exceeded prior to the next i
scheduled snubber service life review, the snubber service life shall be re-evaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled i
service life review. This re-evaluation, replacement or recondition-ing shall be indicated in the records.
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NORTH ANNA - UNIT 1 3/4 7-32 Amendment No. #p, 71
.(Next page is 3/4 7-67)
THIS PAGE INTENTIONALLY LEFT BLANK l
NORTH ANNA - UNIT 1 3/4 7-67 Amendment No. 71
l PLANT SYSTEMS 3/4.7.11 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.11.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material, shall be free of greater than or equal to 0.005 microcuries of removable contamination.
APPLICABILITY: At all times.
ACTION:
a.
Each sealed source with removable contamination in excess of the above limits shall be immediately withdrawn from use and:
1.
Either decontaminated and repaired, or 2.
Disposed of in accordance with Commission Regulations.
b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.11.1.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
a.
The licensee, or b.
Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
4.7.11.1.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below, a.
Sources in use - At least once per six months for all sealed sources containing radioactive materials, i
l' l NORTH ANNA - UNIT 1 3/4 7-68 Amendment No.16 L
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I PLANT SYSTEMS BASES 3/4.7.5 ULTIMATE HEAT SINK I
The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) pro-vide nomal'cooldown of the facility, or 2) to mitigate the effects of l
l accident conditions within acceptable limits.
The limitations on minimum water level and maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature and is con-sistent with the recomendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants", March 1974.
3/4.7.6 FLOOD PROTECTION The limitation on flood protection ensures that facility protective actions will be taken (and operation will be terminated) in the event of flood conditions. The limit of elevation 256 feet Mean Sea Level USGS datum is based on the maximum elevation at which facility flood control 4
measures provide protection to safety related equipment.
i 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS The OPERABILITY of the control room ventilation system ensures that
- 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable.for opera-tions personnel during and following all credible accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equiva-
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lent. This limitation is consistent with the requirements of General 1
Design Criteria 19 of Appendix "A",10 CFR 50.
3/4.7.8 SAFEGUARDS AREA VENTILATION SYSTEM The OPERABILITY of the safeguards area ventilation system ensures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environ-ment.- The operation of this system and the resultant effect on offsite dosage calculations was assumed in the~ accident analyses.
i NORTH ANNA - UNIT 1~
B 3/4 7-5 i
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i PLANT SYSTEMS t
BASES f
3/4.7.9.1 AND 3/4.7.9.2 RESIDUAL HEAT REMOVAL SYSTEM (RHR) i The OPERABILITY of tne RHR system ensures that residual heat removal capability is available below 350 F following plant shutdown. The RHR system is not part of the ECCS system.
3/4.7.10 SNUBBERS The snubbers defined in Technical Specification 3.7.10 are required OPERABLE to ensure that the structural integrity of the reactor ccalant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this 4
inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
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The visual inspection frequency is based upon maintaining a constant
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level of snubber protection to systems. Therefore, the required inspection i
interval varies inversely with the observed snubber failures and is determined j
by the number of inoperable snubbers found during an inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early f
inspections performed before the original required time interv'41 has elapsed l
(nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval l
1 will override the previous schedule.
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When the cause of the rejection of a snubber is clearly established and
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l remedied for that snubber and for any other snubbers that may be generically i
susceptible, and verified by inservice functional testing, that snubber may be i
exempted from being counted as inoperable. Generically susceptible snubbers i
are those which are of a specific make or model and have the same design 3
features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.
When a snubber is found inoperable,'an engineering evaluation is performed, i
in addition to the determination of the snubber mode of failure, in order to i
determine if any safety-related component or system has been adversely affected j
by the inoperability of the snubber. The engineering evaluation shall deter-mine whether or not the snubber mode of failure has -imparted a significant -
effect or degradation on the supported component or system.
i To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally te:ted during plant i
l shutdowns at 13 month intervals. Observed failures of these sample snubbers l
shall require functional testing of additional units.
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NORTH ANNA - UNIT 1 B 3/4 7-6 Amendment No. 33, 7) 6 V
ADMI'NISTRATIVE CONTROLS Records and drawing changes reflecting facility design modifications a.
made to systens and equipnent described in the Final Safety Analysis
- Report, b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
1 Records of facility radiation and contamination surveys.
c.
d.
Records of radiation exposure for all individuals entering radiation control areas.
Records of gaseous and liquid radioactive material released to the e.
environs.
f.
Records of transient operational cycles for those facility components identified in Table 5.9-1.
g.
Records of reactor tests and experiments.
h.
Records of training and qualification for current members of the plant staff.
1.
Records of in-service inspections performed pursuant to these Techni-s cal Specifications.
j.
Records of Quality Assurance activities required by the QA Manual.
k.
Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59.
1.
Records of meetings of the SNSOC.
Records of meetings of the System Nuclear Safety and Operating m.
Committee to issuance of Amendment No. 30.
Records of the service lives of all hydraulic and mechanical snubbers n.
required to be OPERABLE by Technical Specification 3.7.10 including the date at which the service life commences and associated in tion and maintenance records.
Records of secondary water sampling and water quality.
o.
Records of Environmental Qualification which are covered under t p.
provisions of Paragraph 6.13.
Records of analyses required by the radiological environmental moni-q.
toring program that would pennit evaluation of the accuracy of the analysis at a later date.
This would ' include procedures eifective at specified times and QA records showing that these procedures were followed.
NORTH ANNA - UNIT 1 6-23 Amendment No. 38, 33,/gf/, 71
r ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared con-l sistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radia-tion exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or "alars signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 ares /hr but less than
.1000 arem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit.* Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
This individual shall be responsible for providing positive control over the activities within the area and shall perfom periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.
6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 ares /hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or
-the Plant Health Physicist.
" Health Physics personnel shall be exempt from the RWP issuance require-ment during the performance of their assigned radiation protection I
I duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
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NORTH ANNA - UNIT 1 6-24 Amendment No.76,48,4 g l f
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON. D. C. 20555
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VIRGINIA ELECTRIC AND POWER COMPANY i
OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 i
NORTH ANNA POWER STATION, UNIT NO. 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE
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Amendment No. 57 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 19, 1985, complies with the i
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; i
B.
The facility will operate in conformity with the application, i
the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized l
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 Comission'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 license anendment, 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. 57. 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 l
Date of Issuance:
November 20, 1985 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 57 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 7-25 3/4 7-25 3/4 7-26a 3/4 7-26 3/4 7-26b 3/4 7-27 3/4 7-26c 3/4 7-28 3/4 7-26d 3/4 7-29 3/4 7-27 thru 3/4 7-50 B 3/4 7-6 B 3/4 7-6 6-23 6-23
1 PLANT SYSTEMS 3/4.7.10 SNUBBERS LIMITING CONDITION FOR OPERATION 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 system would have an adverse effect on any safety related system.
APPLICABILITY: MODES 1, 2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
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 inoperable snubber (s) to CPERABLE status and perform an engineering evaluation per Specification 4.7.10.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4
4.7.10 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of 1
Specification 4.0.5.
a.
Visual Inspections l
The first inservice visual inspection of snubbers shall be perfbrmed after four months but within 10 months of commencing POWER OPERATION and shall include the snubbers defined in 3.7.10.
Iflessthantwo(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-l quent vTsual inspections shall be performed in accordance with the following schedule:
)
No. Inoperable Snubbers Subsequent Visual per Inspection Period Ins)ection Period *#
O H months + 257, 1
12 months T 25%
l 2
6 months T 25%
3, 4 124 days + Y5%
5,6,7 62 days T 25%
8 or more 31 days T 25%
Early inspections (i.e. those performed before 75% of the current inspection period has elapsed) may be used to set new reference surveil-lance dates for the current inspection period. However, the results of such early inspections cannot be used to increase the current inspection 3
period (period may only stay the same or decrease as detemined by the table in 4.7.10.a).
- The inspection interval shall not be lengthened more than one step at a time.
4
- The provisions of Specification 4.0.2 are not applicable.
NORTH ANNA - UNIT 2 3/4 7-25 Amendment No. JJ, 57
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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 ars secur6, 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 established 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.
However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval, All snubbers connected to an inoperable conunon hydraulic fluid reservoir shall be counted as inoperable snubbers.
c.
Functional Tests At least once per 18 months during shutdown, a representative sam le of that number of snubbers which follows the expression 35 [1 +
where c=2 is the allowable number of snubbers not meeting the acceptance criteria selected by the operator, shall be functionally tested either in-place or in a bench test. For each number of snubbers above c which does not meet the functional test acceptance criteria for Specification 4.7.10.d or 4.7.10.e, an additional sample selected according to the expression 35(1+f)(c 1)
(a - c) g shall be functionally tested, where a is the total number of snubbers found inoperable during the functional testing of the representative sample.
Functional testing shall continue according to the expression b[35(1+f)(c 1 ) ] where b is tha number of snubbers found l
inoperable in the previous re-sample, until no additional inoperable snubbers are found within a sample or until all snubbers have been functionally tested.
NORTH ANNA - UNIT 2 3/4 7-26 Amendment No. U, 57 l
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
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 representative 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 a
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Snubbers within 10 feet of the discharge from a safety 1
relief valve.
1 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 design subject to the same defect shall be functionally i
tested. This testing requirement shall be independent of the require-i ments stated above for snubbers not meeting the functional test accept-
~
ance criteria, 1
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- Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Consnission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was perfonned to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
I NORTH ANNA - UNIT 2 3/4 7-27 Amendment No. D, M, 57 l
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4 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 veri fied.
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.
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 i
A record of the service life of each snubber, the date at which the designated service life connences and the installation and maintenance i
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. 13, 14, 57 l
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
At least once per 18 months thereafter, the installation and naintenance records for each snubber defined in 3.7.10 shall be reviewed to verify j
that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.
If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be re-evaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be indicated in the records.
f NORTH ANNA - UNIT 2 3/4 7-29 Amendment No. J;, 7A,57
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(Next page is 3/4 7-51)
i PLANT SYSTEMS BASES 3/4.7.5 ULTIMATE HEAT SINK The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal i
cooldown of the facility, or 2) mitigate the effects of accident conditions within acceptable limits.
The limitations on minimum water level and maximum temperature are based 1
i on providing a 30 day cooling water supply to safety related equipment without j
exceeding their design basis temperature and is consistent with the recomenda-1 tions of Regulatory Guide 1.27. " Ultimate Heat Sink for Nuclear Plants",
March 1974.
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3/4.7.6 FLOOD PROTECTION The limitation on flood protection ensures that facility protective actions will be-taken (and operation will be terminated) in the event of flood l
conditions. The limit of elevation 256 feet Mean Sea Level USGS datum is based on the maximum elevation at which facility flood control measures provide protection to safety related equipment.
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3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS i
The OPERABILITY of the control room ventilation system ensures that 1) the i
ambient air temperature does not exceed the allowable temperature for contin-uous duty rating for the equipment and instrumentation cooled by this system 4
'and 2) the control room will remain habitable for operations personnel during
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and following all credible accident conditions. The OPERABILITY of this j
system in conjunction with control room design provisions is based on limiting j
the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. This limitation is consistent'with the requirements of General Design Criteria 19 to Appendix "A",10 CFR 50.
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f 3/4.7.8 SAFEGUARDS AREA VENTILATION SYSTEM The OPERABILITY of the safeguards area ventilation system ensures that l
radioactive materials leaking from the ECCS equipment within the pump room i
following a LOCA are filtered prior.to reaching the environment. Cumulative
{
operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over ~a 31 day period 6
is sufficient to reduce the buildup of moisture on the adsorbers and HEPA i
filters. The operation of this system and the resultant effect on offsite l
dosage calculations was assumed in the accident analyses.
NORTH ANNA - UNIT 2 8 3/4 7-5 t
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PLANT SYSTEMS BASES 3/4.7.9.1 AND 3/4.7.9.2 RESIDUAL HEAT REMOVAL SYSTEM (RHR)
The OPERABILITY of the RHR system ensures that residual heat removal capa-bility is available below 350'F following plant shutdown. The RHR system is not part of the ECCS system.
3/4.7.10 SNUBBERS The snubbers defined in Technical Specification 3.7.10 are required OPERABLE l to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to ceter-mine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or nodel and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.
When a snubber is found inoperable, an engineering evaluation is perfomed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imprted a significant effect or degradation on the supported component or system.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals. Observed failures of these sample snubbers shall require functional testing of additional units.
- o. 13, 57
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ADMINISTRATIVE CONTROLS (Continued) g.
Records of reactor tests and experiments.
h.
Records of training and qualification for current members of the plant staff.
- i. Records of in-service inspections performed pursuant to these Technical Specifications.
- j. Records of Quality Assurance activities required by the QA Manual.
k.
Records of the service life of all hydraulic and mechanical snubbers required to be operable by Technical Specification 3.7.10 including l
the date at which the service life commences and associated installa-tion and maintenance records.
1.
Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59.
m.
Records of meetings of the SNSOC.
Records of meetings of the System Nuclear Safety and Operating n.
Committee to issuance of Amendment No. 11.
Records of secondary water sampling and water quality.
o.
p.
Records for Environmental Qualification which are covered under the provisions of Paragraph 2.C(4)(e) of License No. NPF-7.
q.
Records of analyses required by the radiological environmental monitor-ing program that would permit evaluation of the accuracy of the analysis at a later date. This would include procedures effective at specified times and QA records showing that these procedures were followed.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 arem/hr but less than 1000 mres/hr shall be barricaded and conspicuously posted as a high radiation area and entrance NORTH ANNA - UNIT 2 6/23 Amendment No. JJ, JJ, JA, 57
ADMINISTRATIVE CONTROLS (Continued) thereto shall be controlled by requiring issuance of a Radiation Work Permit *.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them, An individual qualified in the protection procedures who is equipped c.
with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Phy;icist in the Radiation Work Permit.
6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administra-tive control of the Shift Supervisor on duty and/or the Plant Health Physicist.
']
- Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt f rom the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry in high radiation areas.
s NORTH ANNA - UNIT 2 6-24 Amendment No. 31 l
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