ML20133C944
| ML20133C944 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 09/30/1985 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20133C948 | List: |
| References | |
| NUDOCS 8510070541 | |
| Download: ML20133C944 (11) | |
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UNITED STATES k
NUCLEAR REGULATORY COMMISSION O
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DUKE POWER COMPANY DOCKET N0. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated April 9, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; 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 hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 46, are hereby incorporated into this license.
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The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
4 FOR THE NUCLEAR REGULATORY COMMISSION U
3_Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
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Attachment:
Technical Specification Changes Date of Issuance; September 30, 1985 i
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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.27 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated April 9, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; 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 hereby amended by page changes to the Technical Specifications as indicated 'n the attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 27, are hereby incorporated into this license.
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4 The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.
3.
This license amendment 's effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Elinor G. Adensam, Chief icensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance: SePtenber 30, 1985
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ATTACHMENT TO LICENSE AMENDMENT N0.46 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 27 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with' the enclosed pages. 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.
Amended Overleaf Page Page 3/4 7-20 3/4 7-19 3/4 7-29 3/4 7-30 B3/4 7-5 B3/4 7-6
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
No. Inoperable Snubbers of Each Time Until Subsequent Type Found During Inspection Visual Inspection *#
0 18 months i 25%
1 12 months i 25%
2 6 months i 25%
3 3,4 124 days i 25%
E 5,6,7 62 days i 25%
8 or more 31 days i 25%
c.
Refueling Outage Inspections At each refueling, the systems which have the potential for a severe 3
dynamic event, specifically, the main steam system (upstream of the main steam isolation valves) the main steam safety and power operated relief valves and piping, auxiliary feedwater system, main steam supply to the auxiliary feedwater pump turbine, and the letdown and charging portion of the CVCS system shall be inspected to determine if there has been a severe dynamic event.
In case of a severe dynamic event, mechanical snubbers in that system which experienced the event shall be inspected during the refueling outage to assure that the mechanical snubbers have freedom of movement and are not frozen up.
The inspection shall consist of verifying freedom of motion using one of the following:
(1) manually induced snubber movement; j
(2) evaluation of in place snubber piston setting; (3) stroking the mechanical snubber through its full range of travel.
If one or more mechanical snubbers are found to be frozen up during this inspection, thos2 snubbers shall be replaced or repaired before returning to power.
The requirements of Specification 4.7.8b. are independendent of the requirements of this specification, d.
Visual Inspection Acceptance Criteria Visual inspections shall verify:
(1) that there are no visible indications of damage or impaired OPERABILITY, and (2) attachments to the foundation or supporting structure are secure.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERAEl.E for the purpose of establishing the next visual inspection interval, provided that:
(1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible;
- The inspection interval for each type of snubber shall not be lengethened more than one step at a time unless a generic problem has been identified and corrected; in that event the inspection interval may be length _ened one step the first time and two steps thereafter if no inoperable snubbers of that type are found.
- The provisions of Specification 4.0.2 are not applicable.
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McGUIRE - UNITS 1 and 2 3/4 7-19
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.
Visual Inspection Acceptance Criteria (Continued) and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.8f.
When a fluid port of a hydraulic snubber is found to be uncovered the snubber shall be declared inoperable and shall not be determined OPERABLE via functional testing unless the test is started with the piston in the as-found setting, extending the piston rod in the tension mode direction.
All snubbers conntated to an inoperable i
common hydraulic fluid reservoir shall be counted as inoperable snubbers.
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Functional Tests During the first refueling shutdown and at least once per refueling thereafter, a representative sample of snubbers shall be tested using one of the following sample plans. The sample plan shall be selected prior to the test period and cannot be changed during the test period.
The NRC shall be notified of the sample plan selected.
prior to the test period.
1)
At least 10% of the snubbers required by Specification 3.7.8 shall be functionally tested either in place or in a bench l
test.
For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.8f., an additional 10%
of the snubbers shall be functionally tested until no more failures are found or until all snubbers have been functionally tested; or 2)
A representative sample of the snubbers required by Specifica-tion 3.7.8 shall be functionally tested in accordance with Figure 4.7-1.
"C" is the total number of snubbers found not meeting the acceptance requirements of Specification 4.7.8f (failures). The cumulative number of snubbers tested is denoted by "N."
Test results shall be plotted sequentially in the order of sample assignment (i.e., each snubber shall be plotted by its order in the random sample assignments, not by the order of testing).
If at any time the point plotted falls in the " Accept" region, testing of i'nubbers may be terminated.
When the point plotted lies in the " Continue Testing" region, additional snubbers shall be tested until the psint falls in the
" Accept" region, or all the snubbers required by Specifica-tion 3.7.8 have been tested. Testing equipment failure during functional testing may invalidate that d d s testing and allow that day's testing to resume anew at a later time, providing all snubbers tested with the failed equipment during the day of equipment failure are retested; or 3)
An initial representative sample of fifty-five (55) snubbers shall be functionally tested.
For each snubber which does not meet the functional test acceptance criteria, another sample of McGUIRE - UNITS 1 and 2 3/4 7-20 Amendment No. 46 (Unit 1)
Amendment No. 27 (Unit 2)
PLANT SYSTDIS 10 9
8 7
6 C
5 4
CONTINUE
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TESTING
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ACCEPT 1
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0 10 20 30 40 50 60 70 80 90 100 I
N FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST McGUIRE - UNITS 1 and 2 3/4 7-29 Amendment No. 46 (Unit 1)
Amendment No. 27 (Unit 2)
PLANT SYSTEMS 3/4.7.9 SEALED SOURCE CONTAMINATION
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LIMITING CONDITION FOR OPERATION 3.7.9 Each sealed source containing radioactive material either in excess of l
100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha cmitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination.
APPLICABILITY: At all times.
ACTION:
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a.
With a sealed source having removable contamination in excess of the above limits', immediately withdraw the sealed source from use and either:
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Decontaminate and repair the sealed source, or 2.
Dispose of the sealed source in accordance with Commission Regulations.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
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SURVEILLANCE REQUIREMENTS 4.7.9.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
I a.
The licensee, or b.
Other persons specifically authorized by the Commission or an Agreement State.
The test method sh'all have a detection sensitivity of at least 0.005 ciicrocurie per test sample.
4.7.9.2 Test Frequencies - Each category of sealed sources (excluding l
startup sources and fission detectors previously subjected to core flux) shall l
be tested at the frequency described below.
l a.
Sources in use - At least once per 6 months for all sealed sources containing radioactive materials:
1)
With a half-life greater than 30 days (excluding Hydrogen 3),
and 2)
In any form other than gas.
McGUIRE - UNITS 1 and 2 3/4 7-30
BASES 3/4.7.8 SNUBBERS All snubbers are required OPERABLE 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.
j Snubbers are classified and grouped by design and manufacturer but not by size.
For example, mechanical snubbers utilizing the same design features of the 2 kip, 10 kip, and 100 kip capacity manufactured by Company "A" are of the same type.
The same design mechanical snubbers manufactured Company "B" for the purposes of this specification would be of a different type, as would hydraulic snubbers from either manufacturer.
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 determine the next inspection.
However, the results of such early i
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.
To provide assurance of snubber functional reliability one of the three sampling and acceptance criteria methods are used:
1.
Functionally test 10% of a type of snubber with an additional 10%
tested for each functional testing failure, or 2.
Functionally test a sample size and determine sample acceptance or continue testing
- using Figure 4.7-1, or l
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Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.
Figure 4.7-1 was developed using "Wald's Sequential Probability Ratio Plan" as described in " Quality Control and Industrial Statistics" by Acheson J. Duncan.
Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption l
is presented and, if applicable, snubber life destructive testing was performed to qualify the snubber for the applicable design conditions at either the completion of their fabrication or at a subsequent date.
Snubbers so exempted shall continue to be listed in Tables 3.7-4a and 3.7-4b with footnotes indicating the extent of the exemptions.
- If testing continues to between 100-200 snubbers (or 1-2 weeks) and still the accept region has not been reached, then the actual % of population quality (C/N) should be used to prepare for extended or 100% testing.
McGuire - UNITS 1 and 2 8 3/4 7-5 Amendment No.46(Unit 1)
Amendment No.27(Unit 2)
PLANT SYSTEMS
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BASES SNUBBERS (Continued)
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring rrlaced, in high radiation area, in high temperature area, etc...).
The ret,.irement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
The requirements for the maintenance of records and the snubber service life review not intended to affect plant operation.
3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use,
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with Surveillance Requirements commer)surate with the probability of damage to a source in that group.
Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
3/4.7.10 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the Fire Suppression Systems ensures that adequate fire suppression capability is available to confine and er.tinguish fires l
occurring 'in any portion of the facility where safety related equipment is located.
The Fire Suppression System consists of the water system, spray, and/or sprinklers, Halon, and fire hose stations.
The collective capalllity of the Fire Suppression Systems is adequate to minimize potential damage to safety-related equipment and is a major element in the f acility fire protection program.
In the event that portions of the Fire Suppression Systems are inoperable, alternate backup fire-fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
When the inoperable fire-fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an I
alternate means of fire fighting than if the inoperable equipment is the primary means of fire suppression.
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McGUIRE - UNITS 1 and 2 B 3/4 7-6