ML20049J104
| ML20049J104 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/03/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20049J105 | List: |
| References | |
| NUDOCS 8203120074 | |
| Download: ML20049J104 (9) | |
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UNITED STATES 3
o NUCLEAR REGULATORY COMMISSION t;
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l CAROLINA POWER AND LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No. DPR-23 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Carolina Power and Light Company (the licensee) dated March 27, 1 981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I;.
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
I 8203120074 820303 PDR ADOCK 05000261 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-23 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 63, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
Thislicenseamendmentiseffectiveasofthe8dt'eofitsissuance.
I OR THE NUC EAR REGULATORY COMMISSION l..-
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J(s, dev A.t Varg, Chief Operating Reac o s Branch #1 Division of Lie sing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 3,1982 f
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ATTACHMENT TO LICENSE AMENDMENT -
3 AENDMENT NO. 63 TO FACILITY OPERATING LICENSE NO.*DPR-23 l j DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages_
Insert Pages 3.13-1 3.13-1 3.13-2 3.13-2 4.13-1 4.13-1 4.13-2 4.13-2 4.13-3 f
4.13-3 4.13-4 4.13-4
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.aL2 3.13 SHOCK SUPPRESSORS (SNUEBERS)
Applicability Applies to hydraulic shock suppressors (snubbers) as shown in Table 3.13-1.
No mechanical snubbers are installed at the H. B. Robinson Plant.
Obiectives To provide for liniting conditions for operation which ensure the operability of snubbers during plant operation, such that normal operation or plant transients requiring operation of the snubbers will not result in consequences more severe than those previously analyzed.
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Specification 3.13'1 During all modes of operation except cold shutdown and refueling, all snubbers specified in Table 3.13-1 shall ina capable of performing their intended function in the rq'uired manner e
(operable) except as described below:
When the reactor is at hot shutdown or at power and a a.
snubber is determined to be inoperable, an engineering analysis must be conducted within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to determine if the snubber's inoperability has adversely affected the supported co=ponent.
If so, the supported component shall be declared inoperable and appropriate action shall be taken in accordance with the appropriate Technical Specification.
If the supported component has not.been adversely affected, (1) an analysis shall be performed to i
determine if the supported component could be damaged during a future event and, if so, the snubber shall be repaired or replaced within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of finding it inoperable, or (2) the supported component shall be declared inoperable until the snubber is repaired or replaced and appropriate action shall be taken in accordance with the appropriate Technical Specification.
If the analysis demonstrates that the snubber is not needed for the supported component to be adequately protected during normal operation and design events, reactor operation shall continue and the snubber shall be repaired on a routine basis.
b.
If a snubber is determined to be inoperable while the reactor is in cold shutdown, the snubber (if needed for supported component protection) shall be repaired and reinstalled or replaced prior to reactor startup.
e 3.13-1 Amendment No. 63 l
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Snubbers may be added to safety related systems without prior c.
License Amendment to Table 3.13-1 provided that a revision to Table 3.13-1 is included with the next License Amendment request.
Basis Snubbers are designed to prevent unrestrained pipe motion under dynamic loads such as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable snubber is a possible increase in the probability of structural damage to piping as a result of a seismic or other event initiating dynamic loads.
It is, therefore, required that all snubbers required to protect the primary coolant system or any other safety system or component be operable during reactor operation or other periods when severe transients might cause damaging dynamic loads. Because the snubber protection is required only during low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for the engineering analysis and for subsequent necessary repair or replacement of the snubber.
Since plarft *startup should not commence with knowingly defective safety-related equipment, the specifi-cation prohibits startup with inoperable snubbers which are required for safe operation.
The engineering analysis will ensure that the supported component was not damaged while the snubber was inoperable.
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3.13-2 Aniendment No. 63 m
1 4.13 S110CK SUPPRESSORS (SNUBBERS)
Applicahtlity Applies to hydraulic shock suppressors (snubbers) listed in Table 3.13-1.
No nachanical snubbers are installed at the H. B. Robinson Plant.
Objectives To ensure the continued operability of hydraulic snubbers by periodic su rveillance.
Specification 4.13.1 Visual Inspection a.
All hydraulic snubbers whose seal material has been demonstrated by operating experience, lab testing or analysis to be compatible with the, operating environment shall be visually inspected in accordance with the following schedule:
Number of Snubbers Next Required Inspection Found Inoperable Interval During Inspection or During Inspection Interval O
18 months 25%
1 12 months 1 25%
2 6 months 1 25%
3,4 124 days 2 25%
5,6,7 62 days 1 25%
gb8 31 days 2 25%
The required ins'pection interval shall not be lengthened more than one step at a time.
Snubbers may be categorized in two groups, " accessible or
" inaccessible" based on their accessibility for inspection during reactor operation.
These two groups may be inspected independently according to the above schedule.
b.
All hydraulle snubbers whose seal materials are other than ethylene propylene, Viton "A", or.other material that has been demonstrated to be compatible with the operating environment shall be visually inspected for operability every 31 days.
c.
The initial inspection shall be performed within 6 months from the date of issuance of these specifications.
For the purpose of entering the schedule in Specification 4.13.1.a.
it shall be assumed that the facility had been on a 6 month inspection interval.
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4.13-1 Amendment No. 63 i
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Vicual insp2cticns chall varify (1) that thera era na visiblo indicatiens of d;mago or inpsired OPERABILITY, (2) atttchmento 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 sevement and is not frozen up.
Snubbers which appear inopersble as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the affected snubber is functionally tested in the as found condition and determined OPERA 3LE per Specification 4.13.2; T2) the cause of the rejection is clearly established and remedied for that particular snubber. However, when the fluid port of a l
hydraulic snubber is found to be uncovered, the snubber shall I
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 common hydraulic fluid reservoir shall be counted as inoperable snubbers.
4.13.2 FUNCTIONAL TESTING l
a.
Once each refueling cycle, a representative sample of approximately 10% of the hydraulic snubbers shall be functionally tested for operability including verification of proper piston movement, lock up and bleed.
For each snubber found inoperable, an additional 10% of the snubbers of that type shall be functionally tested until no more failures are found or all units have been tested.
b.
A representative sample selected for functional testing shall include the various configurations, operating environments and the range cf size and capacity of snubbers. At least 25% of the snubbers in the representative sample shall include snubbers from the following categories:
Snubbers within 5 feet of heavy equipment (valve, a.
pump, steam generator, etc.).
b.
Snubbers within 10 feet of the discharge from a l
safety / relief valve.
c.
The steam generator snubbers (500,000 lbs. f t. rated capacity) need not be removed for functional testing unless the visual inspection dictates that a snubber be removed for corrective maintenance. The testing requirement for these snubbers can be satisfied by testing the control unit (valve block) instead of the entire snubber.
N d.
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next tes t pe riod.
If a spare snubher 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 snobbers may not be included for the re-sampling.
Q 4.13-2 Amendment No. 63
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If any snubber selected for functional testing either faily e.
to lockup or fails to move, i.e., frozen in place, the cause J
will be evaluated and if caused by manuf acturer or design 1
deficiency all snubbers of the same design subject to the same defect shall be functionally tes ted.
This testing requirement shall he independent of the requirements stated above for snubbers not -ceeting the functional test acceptance criteria.
f.
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 af fected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.
4.13.3 snubber service Life Monitoring A record of the service life of each sn'ubber listed on Table 3.13-1, the da te at which the designated service life commences and the instal?ation and maintenance records on which the service life is based shall be maintained.
Once each refueling cycle, these records shall be reviewed to ensure that the service life will not be exceeded prior to the next review.
If the service life of a snubber will be exceeded prior to the next scheduled revies, the snubber's service life can be reevaluated in order to possibly extend it or the snubber shall be reconditioned or replaced.
This reevaluation, replacement, or reconditioning shall be indicated in the records.
Basis All safety-related hydraulic snubbers are visually inspected for overall integrity and operability. The inspection will include verification of proper orientation, adequate hydraulic fluid level, and proper attachment of snubber to piping and structures.
Experience at operating facilities has shown that the required surveillance program should assure an acceptable level of snubber performance provided j that the seal materials are compatible with the operating environment.
Viton "A" and ethylene propylene seal material have been demonstrated by lab tests and operating experience to be compatible with nuclear plant operating environments.
Snubbers containing seal material which has not been demonstrated by operating experience, lab tests or analysis to be compatible with the operating environment shall be inspected mofe frequently (every month) until material compatibility is confirmed or an appropriate changeout is-completed.
4.13-3 Amendment No. 63 t
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b The visual inspection frequency is based upon maintaining a constant level of snubber protection.
Thus the required inspection interval varies inversely with the observed snubber failures. The number of inoperable snubbers found during a required visual inspection determines the time interval for the next required inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next ins pe ct ion.
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.
A snubber which appears inoperable as a result of a visual inspection may be declared operable if it passes a functional test and the cause of the rejection is clearly established and remedied for that particular raubber und for other snubbers that may be generically susceptible.
Generically susceptible snubbers are those which are of a specific make or model 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.
To further increase the assurance of snubber reliability, functional tests should be performed once each refueling cycle.
These tests will include stroking of the snubbers to verify proper piston move =ent, lock up, and ble ed. Ten percent of the snubbers listed on Table 3.13-1 represent an adequate sample for such tests.
Observed failures of these samples shall require testing of additional units.
Periodic functional testing of the steam generator snubbers (as a unit) is not required due to their large size and difficulty of removal. By testing the smaller and more easily removable control unit for each snubber, the operability of these large bore snubbers can be ensured.
When a snubber is found inoperable (visual or functional), an engineering evaluation is performed, 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's mode of failure has imparted a significant effect or degradation on the supported component or system.
The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber,
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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
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evaluation in view of their age and operating conditions. These records will provide statistical b'ases for future adjustments of snubbers' service lives. The review of the snubber's service lives and necessary reconditioning or replacement shall take place once per operating cycle probably during the refueling outage.
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l 4.13-4 Amendment No. 63
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