ML13330A430
| ML13330A430 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/21/1981 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13330A428 | List: |
| References | |
| NUDOCS 8112280328 | |
| Download: ML13330A430 (12) | |
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Page 2 of' 4 SNUBBERS IN SNUBBERS HIGI RADIATION ESPECIALLY SNUBBERS AREA DURING D11:F I CULT ACCE-SS IBLE SNUBBER No.
LOCATION LINE No.
SIIUTDOWN*
O REMOVE CATEGORY**
(A OR 1) 1-S-SW-6, 7-1 Main Steam 6
YES 1-S-SW-6-1 Piping System YES 1-S-SW-6-2 YES I
1-S-SW-6-3 YES 1-S-SW-6-4 YES 1-S-SW-6-5 YES 1-S-SW-6-6 YES 1-S-SW-7-1 Main Steam 7
YES 1-S-SW-7-2 Piping System YES 1-S-SW-7-3 YES 1-S-SW-7-4 YES 1-S-SW-7-5 YES 1-S-SW-7-6 2-9-SW-5 Main Steam 9
NO A
Piping System 6-15-SW-5 Main Steam 15 NO A
6-15-SW-6 Piping System NO A
2-S-SW-17-1 Main Steam 17 NO A
2-S-SW-17-2 Piping System NO A
2-S-SW-17-4 NO A
5-S-17-SW-6 NO A
5-S-17-SW-9 NO A
2-S-SW-18-1 Main Steam 18 NO A
2-S-SW-18-2 Piping System NO A
2-S-SW-18-4 NO A
6-S-18-SW-6 NO A
6-S-18-SW-8 2-S-50-SW-1 Main Steam 50 NO A
2-S-50-SW-2 Piping System NO A
Page 3 of 4 SNUBBERS IN SNUBBERS HI GHI RAD I AT I ON ESPEC I ALLY SNUBBERS AREA DURING DIFFICULT ACCESSIBLE SNUBBER No.
LOCATION LINE No.
IIUIDOWN*
TO REMOVE CATEGORY**
(A OR 1) 2-S-51-SW-1 Main Steam 51 NO A
2-S-51-SW-2 NO A
1-S-SW-391-1 Feedwater 391 YES 1-S-SW-391-2 Piping System YES 1-S-SW-391-3
.YES 1-S-SW-391-4 YES 1-S-SW-392-1 Feedwater 392 YES 1-S-SW-392-2 Piping System YES 1-S-SW-392-3 YES 1-S-SW-392-4 YES 1-S-SW-392-5 YES 1-S-SW-393-1 Feedwater 392 YES 1-S-SW-393-2 Piping System YES 1-S-SW-393-3 YES 1-S-SW-393-4 YES 1-SW-734-2 Containment 734 YES Spray System T-8-PS-27 Refueling Water 734 & 747 NO A
Piping System 1-S-735-SW-1 Refueling Water 735 YES 2
1 Piping System 1-SC-602R-6 Pressurizer 5035 YES Relief Piping System
Page 4 of 4 SNUBBERS IN SNURBERS HIGH RADIATION ESPECIALLY SNUBBERS AREA DURING DIFFICULT ACCESSIBLE SNUBBER No.
LOCATION LINE No SHUTDOWN*
TO REMOVE CATEGORY" OR INACCESSIBLE (YES OR NO)
(A OR 1) 5-SW-151R-10 Safety Injection 6002 NO 2
A 5-SW-151R-11 Piping System NO 2
A 6-151R-13 Safety Injection 6003 NO 2
A 6-151R-14 Piping System NO 2
A 5-S-1501R-40 Safety Injection 6004 NO A
5-S-1501R-41 NO A
5-SS-1501R-9 NO A
6-1501-R-42 Safety Injection 6005 NO A
6-1501-R-43 Piping System NO A
1-SS-1501R-4 Safety Injection 6006 YES I
1-SS-1501R-5 Piping System YES 1-SS-1501R-3 YES I
1-SS-1501R-6 Safety Injection 6007 YES 1-SS-1501R-7 Piping System YES 1-SS-1501R-1 Safety Injection 6008 YES 1-SS-1501R-2 Piping System YES E-1A Steam Generators YES 2
E-1B YES 2
E-1C YES 2
Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table 3.13.2 is included with the next License Amendment Request.
CATEGORY -
- 1.
First snubber away from each reactor vessel nozzle
- 2.
Snubber within 5 feet of heavy equipment.
- 3.
Snubber within 10 feet of the discharge from a safety relief valve.
TABLE 3.13.2 SAFETY RELATED MECHANICAL SNUBBERS SNUBBERS IN SNUBBERS IIIGH RADIATION ESPECIALLY SNUBBERS AREA DURING DIFFICULT ACCESSIBLE SNUBBER No.
LOCATION LINE No.
SHUTDOWN*
TO REMOVE CATEGORY**
(A OR 1) 5-318-SW-10 Safety-Injection 318 NO A
5-318-SW-11 Piping System NO A
1-6019-SS-2 Safety Injection 734 NO A
7-734-SS-003 Sphere Spray 734 YES I
SA-16-1 No.
1 D/G 1540 NO A
SA-16-2 Intake 1542 NO A
SA-16-3 No.
1 D/G 1544 NO A
SA-16-4 Exhaust NO A
SA-16-5 NO A
SA-16-6 NO 3
A SA-17-1 No.
2 D/G 1547 NO A
SA-17-2 Intake 1549 NO A
SA-17-3 No. 2 D/G 1551 NO A
SA-17-4 Exhaust NO 3
A SA-17-5 NO A
SA-17-6 NO 3
A SA-1 Safety Injection 3122 NO A
Piping System 5-SS-151R-11 Safety Injection 6002 NO A
14-PS-2A Piping System NO A
6-SW-151R-15 6003 NO A
14-PS-20 NO A
Page 2 of 2 SNUBBERS IN SNUB8ERS HIGH RADIATION ESPECIALLY SNUBBERS AREA DURING DIrFICUJT ACCESSIBLE SNUBBER No.
LOCATION LINE No.
SHUTDOWN*
TO REMOVE CATEGORY**
(A OR I) 2-SC-1501R-03 Safety Injection 6005 A
6-SC-1501R-02 Piping System A
1-SS-1501-11 6006 A
1-SS-1501-R-14 YES 1
I 1-SS-1501-R-10 6008 YES I
1-SS-1501-R-13 YES 1
1-SS-1501-12 Safety Injection 6007 YES 1
1-SS-1501-R-15 Piping System YES 1-6018-SS-006 Safety Injection 6018 YES Piping System YES
.1 1-6019-SS-006 Safety Injection 6019 YES Piping System Modifications to this column due to changes In high radiation areas may be made without prior License Amendment provided that a revision to Table 3.13.2 is included with the next License Amendment Request.
CATEGORY -
- 1.
First snubber away from each reactor vessel nozzle
- 2.
Snubber within 5 feet of heavy equipment.
- 3.
Snubber within 10 feet of the discharge from a safety relief valve.
0.I
4.14 SHOCK SUPPRESSORS (SNUBRERS) SURVEILLANCE Applicability:
Applies to surveillance of safety related snubbers delineated in Tables 3.13.1 and 3.13.2 Objective:
To ensure the operability of safety related snubbers.
Specification:
Each snubber listed in Tables 3.13.1 and 3.13.2 shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 3.13.
A. Visual Inspections Visual inspections shall be performed in accordance with the following schedule:
No. of Snubbers Found Inoperable During Inspection or During Inspection Subsequent Visual Interval Inspection Period*
.0 18 months + 135 days 1
1? months + 90 days 2
6 months + 45 days 3, 4 124 days
+
31 days 5, 6, 7 62 days
+
16 days 8 or more 31 days
+
8 days 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, the subgroups - mechanical and hydraulic - may be inspected independently.
All hydraulic snubbers, with seal material not fabricated from ethylene propylene or other materials demonstrated compatible with the operating environment, shall be visually inspected for operability at intervals of roughly half the duration that the seal material has been demonstrated to remain operable or the Visual Inspection Period, if less.
For materials of uncertain compatibility with the environmelt, the seals shall be visually inspected every 31 + 8 days.
(As of mid-1981, there were no such -eals.)
- The inspection interval shall not be lengthened more than one step at a time.
-2 B. Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to those 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 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 4.14.D or 4.14.E, as applicable.
C. Functional Tests At least once per refueling cycle shutdown, a representative sample (10% of the total, the next larger integer number, 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 4.14.0 or 4.14.E, an additional 10% of that type of snubber shall be 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 50,000 pounds, i.e., E-1A, E-1B and E-1C. 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
-3 Snubbers identified in Table 3.13.1 and 3.13.2 as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample. Tables 3.13.1 and 3.13.2 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-s ampl i ng.
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.
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 1lad, the ability of the snubber to withstand load without displacement shall be verified.
-4 E. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify, after visual examination for damage, that the snubbers have freedom of movement by performing a manual test over the range of stroke in both compression and tension.
(Per IE Bulletin 81-01)
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 is based shall be maintained as required by Specification 6.10.2.k.
Concurrent with the first inservice visual inspection and at least once per refueling outage thereafter, the installation and maintenance records for each snubber listed in Tables 3.13.1 and 3.13.2 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 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.
HSS:2135
6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
- a. Records and logs of facility operation covering time interval at each power level.
- b. Records and logs of principle maintenance activities, inspections, repair and replacement of principle items of equipment related to nuclear safety.
- c. Reportable Occurrences.
- d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
- e. Repords of reactor tests and experiments.
- f. Records of changes make to Operating Procedures.
- g. Records of radioactive shipments.
- h. Records of sealed source leak tests and test results, in units of microcuries, for leak tests performed pursuant to Specification 4.12.
- i. Records of annual physical inventory of all source material of record.
6.10.2 The following records shall be retained for the duration of the Facility Operating License:
- a. Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
- b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
- c. Records of radiation exposure for all individuals tentering radiation control areas.
- d. Records of gaseous and liquid radioactive material released to the environs.
- e. Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
- 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 qxperiments pursuant to 10 CFR 50.59.
- i.
Records of meetings of the OSRC and the NARC.
- j. Records for Engironmental Qualification which are covered under the provisions of paragraph 6.12.
- k. Records of the service lives of all hydraulic and mechanical snubbers listed in Tables 3.13.1 and 3.13.2, 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.
HSS:2462