ML17279A994
| ML17279A994 | |
| Person / Time | |
|---|---|
| Site: | Columbia  (NPF-21-A-054, NPF-21-A-54) |
| Issue date: | 04/11/1988 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17279A995 | List: |
| References | |
| TAC-60471, TAC-60472, NUDOCS 8804210425 | |
| Download: ML17279A994 (10) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
>4 License No. NPF-21 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Washington Public Power Supply System (the Supply System, also the licensee),
dated December 1,
1987 as supplemented by letter dated March 18, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 regulations of the Commission; C.
D.
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 set forth in 10 CFR Chapter I; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-21 is hereby amended to read as follows:
8804210425 880411 PDR ADOCK 05000397:
P PDR (2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
54, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
April ll, 1988 George M'. Knighton., Director Project Directorate V
Division of Reactor Projects - III, IV, V and Special Projects
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued No. Inoperable Snubbers of Each Type on Any System er Ins ection Period 1
2 3,4.
5',6,7 8 or more c.
Visual Ins ection Acce tance Criteria Subsequent Visual Ins ection Period" ¹ 18 months,
+2
, - 0 12 months 2 25K 6 months f 25K 124 days t 25K 62 days 2 25K 31 days t 25X Visual inspections shall verify that: (1) there are no visible indi-cations of damage or impaired, OPERABILITY,'(2) attachments to the foundation or supporting structure are'secure, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are secure.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE 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 on that system that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specification 4.7.4f.
All snubbers. connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.
For those snubbers common to more than one
- system, the OPERABILITY of such snubbers shall be considered in assessing the surveillance schedule for each of the related systems.
d.
Transient Event Ins ection An inspection shall be performed of all hydraulic and mechanical snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a revie~ of operational data and a visual inspection of the systems within 6 months following such an event.
In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using at least one of the following:
(1) manually induced snubber movement; or (2) evaluation of in-place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.
"The inspection interval for each type of snubber on a given system shall not be lengthened more than one step at a time unless a generic problem has been identified and corrected; in that event the inspection interval may be lengthened one step the first time and two steps thereafter if no inoperable snubbers of that type are found on that system.
¹The provisions of Specification 4.0.2 are not applicable.
WASHINGTON NUCLEAR UNIT 2 3/4 7-11 Amendment No.
40
PLANT SYSTEMS 0
SURVEILLANCE RE UIREMENTS.
Continued e.
Functional Tests During the first refueling shutdown and at least once per 18 months thereafter during shutdown, 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 Regional Administrator shall be notified in writing of the sample plan selected prior to the test period or the sample plan used in the prior test period shall be implemented:
1)
At least lOX of the total of each type of snubber shall be functionally tested either in-place or in a bench test.
For each snubber of a type that does not meet the functional test acceptance criteria of Specification-4.7.4f.,
an additional 5X of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type.have been functionally tested; or 2)
A representative sample of 37 snubbers 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 4.7.4f.
The cumulative number of snubbers of a type tested is denoted by "N". If at any time the point plotted falls in the "Accept" region, testing of snubbers may be ter-minated.
When the point plotted lies in the "Continue Testing" region, additional snubbers shall be tested until the point falls in the "Accept" region or all the snubbers have been tested.
Testing equipment failure during functional testing may invalidate that day's testing and allow that day's testing to resume anew at a later time provided all snubbers tested with the failed equipment during the day of equipment failure are retested.
The representative sample selected for the functional test sample plans shall be randomly selected from the snubbers of each type and reviewed before beginning the testing.
The review shall ensure, as far as practicable, that they are representative of the various con-figurations, operating environments, range of size, and capacity of snubbers of each type.
Snubbers placed in the same location as snubbers which failed the previous functional test shall be retested at the time of the next functional test but shall not be included in
, WASHINGTON NUCLEAR UNIT 2 3/4 7-12 Amendment No. 54
0 PLANT SYSTEMS SURVEILLANCE RE UIREMENTS'ontinued) e.
Functional Tests (Continued) the sample plan.
If during the functional testing, additional testing is required due to failure of snubbers, the unacceptable snubbers may be categorized into test failure mode group(s).
A test failure mode group shall include all unacceptable snubbers that have a given failure mode and all other snubbers subject to the same failure mode.
Once a test failure mode group has been established, it can be separated for continued testing apart from the general population of snubbers.
However, all the unacceptable snubbers in this failure mode group shall be counted as one unacceptable snubber for additional testing in the general population.
Testing in the failure mode group shall be based on the number of unacceptable snubbers and shall continue until no more failures are found or all snubbers in the failure mode group have been tested.
Any additional unacceptable snubbers found in the test failure mode group shall be counted for continued testing only for that test failure mode group.
Functional Test Acce tance Criteria g.
The snubber functional test shall verify that:
1)
Activation (restraining action) is achieved within the specified range in both tension and compression; 2)
Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range; 3)
Where required, the force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel; and I
4)
For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement.
Testing methods may be used to measure parameters indirectly or para-meters other than those specified if those results can be correlated to the specified parameters through established methods.
Functional Test Failure Anal sis An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure.
The results of this evaluation shall be used, if MASHINGTON NUCLEAR - UNIT 2 3/4 7-13 Amendment No. 54
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) g.
h.
Functional Test Failure Anal sis (Continued) applicable, in selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers irrespective of type which may be subject to the same failure mode.
For the snubbers found inoperable, an engineering evaluation shall be performed on the components to which the inoperable snubbers are attached.
The purpose of this engineering evaluation shall be to determine if the components to which the inoperable snubbers are attached were adversely affected by the inoperability of the snubbers in order to ensure that the component remains capable of meeting the designed service.
If any snubber selected for functional testing either fails to lock up or fails to move, i. e., frozen-in-place, the cause will be evaluated and, if caused by manufacturer or design deficiency or unexpected transient event, all snubbers of the same type subject to the same defect shall be evaluated in a manner (stroking, testing, replacement etc.) to ensure their operability.
This evaluation requirement shall be independent of the requirements stated in Specification 4.7.4e. for snubbers not meeting the functional test acceptance criteria.
Functional Testin of Re aired and Re laced Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced.
Replacement snubbers and snubbers which have repairs which might affect the functional test results shall be tested to meet the functional test criteria before installation in the unit.
Mechanical snubbers shall have met the acceptance criteria subsequent to their most recent
- service, and the freedom-of-motion test must have been performed within 12 months before being installed in the unit.
Snubber Service Life Pro ram The service life of hydraulic and mechanical snubbers shall be moni-tored to ensure that the service life is not exceeded between sur-veillance inspections.
The maximum expected service life for various
- seals, springs, and other critical parts shall-be determined and
'established based on engineering information and shall be extended or shortened based on monitored test results and failure history.
Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE.
The parts replacements shall be documented and the documentation shall be retained in accordance with Specification
- 6. 10. 2.
MASHINGTON NUCLEAR " UNIT 2 3/4 7-14 Amendment No. 54
10 CONTINUE TESTlNG
~Q G
ACCEPT 0
10 20 30 40 50 60 70 80 90 100 N
FIGURE 4.7-1 SAMPLE PLAN 2)
FOR SNUBBER FUNCTIONAL TEST WASHINGTON NUCLEAR - UNIT 2 3/4 7-15 Amendment No.
54
PLANT SYSTEMS 3/4. 7. 5 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.5 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcurie of alpha emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination.
APPLICABILITY: At all times.
ACTION:
a 0 With a sealed source having removable contamination in excess of the above limit, withdraw the sealed source from use and either:
1.
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.
SURVEILLANCE RE UIREMENTS 4.7.5. 1 Test Re uirements - 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 microcurie per test sample.
4.7.5.2 Test Fre uencies - Each category of sealed
- sources, excluding startup sources and fission detectors previously subjected to core flux, shall be tested at the frequency described below.
Sources in use - At least once per 6 months for all sealed sources containing radioactive material:
1..
With a half-life greater than 30 days, excluding Hydrogen 3, and 2.
In any form other than gas.
WASHINGTON NUCLEAR - UNIT 2 3/4 7-16
PLANT SYSTENS BASES 3/4.7. 4 SNUBBERS (Continued) failures and initiating events is constant with time and that the failure of any snubber on that system could cause the system to be unprotected and to result in failure during an assumed initiating event.
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 inspections performed before the original required time interval has elapsed, (nominal time less 25K) may not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will override the previous schedule.
The acceptance criteria are to be used in the visual inspection to deter-mine OPERABILITY of the snubbers.
For example, if 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.
To provide assurance of snubber functional reliability, one of two functional testing methods are used with the stated acceptance criteria:
1.
Functionally test 10K of a type of snubber with an additional 5X 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.
WASHINGTON NUCLEAR - UNIT 2 8 3/4 7-3 Amendment No.
54
PLANT SYSTEMS BASES SNUBBERS (Continued)
Figure 4.7-1 was developed using "Wald's Sequential Probability Ratio Plan" as described in "guality 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 is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the com-pletion of their fabrication or at a subsequent date.
Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
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 snubbers, seal
- replaced, spring replaced, in high radiation area, in high temperature area, etc.).
The requirement 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 statis-tical bases for future consideration of snubber service life.
3/4.7.5 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, with surveillance requirements commensurate 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 devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
3/4 7.6 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available 'to confine and extinguish fires 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 sprinkler systems, CO~ systems, Halon systems, and fire hose stations.
The collective capability of the fire suppression systems is adequate to minimize potential damage to safety-related equipment and is a major element in the facility fire protection program.
WASHINGTON NUCLEAR - UNIT 2 B 3/4 7-4 Amendment No. 54