ML13316A701
| ML13316A701 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/15/1984 |
| From: | Paulson W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316A700 | List: |
| References | |
| DPR-13-A-081, TAC-55407 NUDOCS 8410170274 | |
| Download: ML13316A701 (10) | |
Text
pR REGOU 1
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY AND SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 81 License No. DPR-13
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The-application for amendment by Southern California Edison Company and San Diego Gas and Electric Company (the licensees) dated July 23, 1984 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, Commission; 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 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.
~~A-01
-2
- 2. 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 Provisional Operating License No. DPR-13 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
, are hereby incorporated in the license. Southern California Edison Company 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 Walter A. Paulson, Acting Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 15, 1984
ATTACHMENT TO LICENSE AMENDMENT NO. 81 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications by removing the following pages and by inserting the enclosed pages. The revised pages contain the captioned amendment number and marginal lines indicating the area of change.
Remove Pages Insert Pages 39g 39g 39h 39h Table 3.13.1 (pages 1-4)
Table 3.13.2 (pages 1 and 2) 601 601 60J 60J 60K-1 60K-1 60K-2 60K-2 88 88
-39g(
3.13 SHOCK SUPPRESSORS (SNUBBERS) OPERABILITY Applicability Applies to safety-related shock suppressors (snubbers).
Objective To define operability requirements of snubbers required to protect safety-related piping from unrestricted motion when subjected to dynamic loading as might occur during a seismic event or severe transient.
Specification A. During MODES 1, 2, 3 and 4 (MODES 5 and 6 for snubbers located in systems required.OPERABLE in those MODES) all snubbers shall be OPERABLE. The only snubbers excluded.
from this requirement are those installed on non-safety-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.
B. 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 4.14.C on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
Basis Snubbers are provided to ensure that the structural *Integrity of the reactor coolant system and all other safety-celated systems is maintained during and following a seismic or other event initiating dynamic loads.
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 th& 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 in-service functional testing, that snubber may be exempted from being counted as inoperable.
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.
Amendment No. p, 31
39h When a snubber is found inoperable, 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 mode of failure has imparted 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 refueling outage intervals. Observed failures of these sample snubbers will require functional testing of additional units.
Snubbers of rated capacity greater than 120,000 pounds are exempt from functional testing requirements because of the impracticability of testing such large units.
Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
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, 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 ope'rating conditions.
These records will provide statisticar bases for future consideration of snubber service life.
The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
Amendment No. ?4. &, 81
~60I1 4.14 SHOCK SUPPRESSORS NUBBERS) SURVEILLANCE Applicability Applies to surveillance of safety-related snubbers.
Objective To ensure the operability of safety-related snubbers.
Specification Each snubber shall be demonstrated OPERABLE by performance of the following augmented in-service inspection program and the requirements of Specification 3.13.
A. Visual Inspections Visual inspections shall be performed in accordance with the following schedule:
No. Inoperable per Inspection Subsequent Visual Period Inspection Period*
0 18 months +
25%
1 12 months +
25%
2 6S'months +
25%
3, 4 124 days
+
25%
5, 6, 7 62 days
+
25%
8 or more 31 days
+.
25%
The snubbers may be categorized into two groups:
Those accessible and those inaccessible during normal reactor operation.
Each group may be inspected independently in accordance with.the above schedule.
Further, tt'e subgroups - mechanical and hydraulic -
may be lispected independently.
B. Visual Inspection Acceptance Criteria
.Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILTY, and (2) attachments to the foundation or supporting structure 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, 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 Specification 4.14.D or 4.14.E, as applicable.
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 common hydraulic fluid reservoir shall be counted as inoperable snubbers.
- The inspection interval shall not be lengthened more than one step at a time.
Amendment 21, 34, S, 81
600 C. Functional Tests At least once per refueling cycle shutdown, a representative sample, 10% of the total, of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test.
For each snubber that does not meet the functional test acceptance criteria of Specification 4.14.D or 4.14.E, an additional 10% 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.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers, exempting snubbers of capacity greater than 120,000 pounds, i.e., E-lA, E-lB and E-lC.
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 five feet of heavy equipment (valve, pump, turbine, motor, etc.);
- 3. Snubbers within.ten feet of the discharge from a safety relief valve.
Snubbers that are especially difficult to removg or are located in high radiation zones during shutdown shall also be included in the representative sample.*
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 functionally tested.
This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
- Permanent or other exemptions from functional testing for individual snubbers
'in these categories may be granted by the Commission only if a justifiable 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.
Anendment No.
S, n
- 60K-1 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 designed 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 displacement shall be verified.
E. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
- 1. The force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel;
- 2. Activation (restraining action) is achieved within the specified 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 verified.
F. Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.k.
Concurrent with the first in-service visual inspection and at least once per refueling cycle shutdown thereafter, the installation and maintenance records for each snubber shall be reviewed to verify 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 Amendment No.
[,
01
-60K-2 shall be reevaluated 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.
Basis:
Refer to the basis given in 3.13 Amendment 'No.
6
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- f. Records of in-service inspections performed pursuant to these Technical Specifications.
- g. Records of Quality Assurance activities as required by the QA Manual.
- h. Records of reviews performed for changes made to procedures or equipment or reviews or tests and experiments pursuant to 10 CFR 50.59.
- j. Records for Environmental Qualification which are covered under the provisions of paragraph 6.12.
- k. Records of the service lives of all safety-related hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.
6.10.3 The following records shall be retained for two years..
- a. Records of facility radiation and contamination surveys.
- b. Records of training of facility personnel.
Amendment No. /,61, 63. 81