ML20033F631
| ML20033F631 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  (NPF-10-A-083, NPF-10-A-83, NPF-15-A-071, NPF-15-A-71) |
| Issue date: | 03/05/1990 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20033F129 | List: |
| References | |
| NUDOCS 9003230117 | |
| Download: ML20033F631 (7) | |
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00 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.41 DOSE EQUlVALENT l-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 1.0pCl/ gram Dose Equivalent 1131 SAN ONOFRE-UNIT 3 3/4 4.??
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TA3'E 4.3-?
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CHANNEL M00ES FOR WHICH
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CHANNEL CHA M L FUNCTIONAL SURVEILLANCE E
INSTRUNENT CHECK CALIBRATI_0h TEST IS REQUIRED "w
u WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM
- a. Hydrogen Monitor (cont'nuous)
D Q(1)
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- b. Oxygen Monitor (continuous)
D Q(2)
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- c. Hydrogen Monitor (periodic)
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- d. Oxygen Monitor (periodic)
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REACTORCOOLANTSYSTE[.
3/4.4.8 PRESSUkE/ TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITING CONDIT!0K FOR OPERATION 4
3.4.8.1 With the reactor vessel head bolts tensioned *, the Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2, 3.4-3, 3.4-4, and 3.4-5 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:
A maximum heatup as specified by Figure 3.4-3 in any 1-hour period a.
with RCS cold leg temperature less than 153'F.
A maximum heatup of 60*F. in any 1-hour period with RCS cold leg temperature greater than 15.2'F.
t b.
A maximum cooldown as specified by Figure 3.4-5 in any 1-hour period with RCS cold leg temperature less than 126'F.
A maximum cooldown of 100*F in any 1-hour period with RCS cold leg temperature greater than 126*F.
A maximum temperature change of 10*F in any 1-hnur period during c.
intervice hydrnstatic and leak testing operations above the heatup ar.d cooldewn limit curves.
d.
A minimum temperature of E6*F to tension reactor vessel head bolts.
With the reactor vessel head bolts detensioned, the Reactor Coolant System i
(except the pressurizer) temperature shali be limited to a maximum heatup or cooldown of 60'F in any 1-hour period.
APPLICABILITY: At all times.
ACTION:
I With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor. Coolant System; determine that the Reactor Coolant System remains acceptable for continued operations or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS T and pressure to less than 200'Fand500 psia,respectively,withintheYE11owing30 hours.
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- With the reactor vessel head bolts detensioned, RCS cold leg temperature may be less than 86'F.
SAN ONOFRE - UNIT 3 3/4 4-28 AMENDMENT NO.71 1
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a TABLE 4.3 '
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RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS o5 E
CHANNEL MODES FOR WHICH.
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CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E
INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED "w
m WASTE GA5 HOLDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM
- a. Hydrogen Monitor (continuous)
D Q(1)
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- b. Oxygen Monitor (continuous)
D Q(2)
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- c. Hydrogen Monitor (periodic)
D Q(1)
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- d. Oxygen Monitor (periodic)
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TABLE 4.3-9 (Continued)
TABLE NOTATION l
During waste gas holdup system operation (treatment for primary system offgases).
(1) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
1.
One volume percent hydrogen, balance nitrogen, and 2.
Four volume percent hydrogen, balance nitrogen.
(2) The CHANNEL CALIBRATION shall include the use of standard gas samples,
containing a nominal:
1.
One volume percent oxygen, balance nitrogen, and 2.
Four volume percent oxygen, balance nitrogen.
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.a SAN ONOFRE - UNIT 2 3/4 3-68 AMENDMENT NO. 83
.e....
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INDEX DESIGN FEATURES SECTION PAGE 5.1-SITE 5.1.1 EXCLUSION AREA..........................................
5-1 5.1.2 LOW POPULATION 20NE.....................................
5 5.1. 3 SITE BOUNDARY FOR GASEOUS EFFLUENTS.....................
5-1 5.1.4 SITE BOUNDARY FOR LIQUID EFFLUENTS......................
5-1 5.2 CONTAINMENT 5.2.1 CONFIGURATION...........................................
5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE.........................
5-1 5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES.........................................
5-6
- 5. 3. 2 CONTROL ELEMENT ASSEMBLIES..............................
5-6 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE.........................
5-6 5.4.2-V0LUME.......................................
5-7 5.5 METEORLOGICAL TOWER LOCATION.................................
5-7 5.6 FUEL STORAGE 5.6.1 CRITICALITY.............................................
5-7 5.6.2 DRAINAGE................................................
5-7 5.6.3 CAPACITY................................................
5-7
5-7 h
SAN ONOFRE-UNIT 2 XV AMENDMENT NO. 83 i
1NDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY...............................................
6-1 6.2 ORGANIZATION 6.2.1 0FFSITE..................................................
6-1 6.2.2 UNIT STAFF..............................................
6-1 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP....................
6-5 6.2.4 SHIFT TECHNICAL ADVISOR.................................
6-5 6.3 UNIT STAFF QUALIFICATIONS....................................
6-5 6.4 TRAINING.....................................................
6-6
- 6. 5 REVIEW AND AUDIT 6.5.1 ONSITE REVIEW COMMITTEE FUNCTION.'............................................
6-6 COMPOSITION............................................
6-6 ALTERNATES...........................................
6-6 MEETING FREQUENCY....................................
6-7 QU0RUM...............................................
6-7 RESP 0NSIBILITIES.....................................
6-7 AUTHORITY............................................
6-8 REC 0RDS..............................................
6-8 6.5.2 TECHNICAL REVIEW AND CONTR0L............................
6-8 6.5.3 NUCLEAR SAFETY GROUP FUNCTION................................................
6-9 COMPOSITION..............................................
6-10 CONSULTANTS.............................................
6-10 REVIEW..................................................
6-10 AUDITS..................................................
6-11 SAN ONOFRE-UNIT 2 XVI AMENDMENT NO. 83 l
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,i INDEX BASES SECTION PAGE 3/4.9.6 REFUELING MACHINE.....................................
B 3/4 9-2 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING...
B 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND C0OLANT CIRCULATION..............
B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM..............
B 3/4 9-3 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL.........................................
B 3/4 9 3/4.9.12 FUEL HANDLING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEM..........................................,,,,
g gjg 9 3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.......................................
B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS...........................
B 3/4 10-1 3/4.10.3 REACTOR COOLANT L00PS.................................
B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT AND REGULATING CEA INSERTION LIMITS....................................
B 3/4 10-1 3/4.10.5 RADIATION MONIT0".ING/ SAMPLING -- DELETED 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS......................................
B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS.....................................
B 3/4 11-1 3/4.11.3 SOLID RADIOACTIVE WASTE -- DELETED 3/4.11.4 TOTAL DOSE -- DELETED 3/4.12 RADIO ENVIRONMENTAL MONITORING -- DELETED 3/4.12.1 MONITORING PROGRAM -- DELETED 3/4.12.2 LAND USE CENSUS -- DELETED-3/4.12.3 INTERLABORATORY COMPARISON PROGRAM -- DELETED SAN ONOFRE-UNIT 2 XIV AMENDMENT NO.83 3
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SECTION PAj{
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TkRE '*E CYCLE........................'.................
I3.4T-i 3 /a. 7. 2 STIAM GENIFATOR FRes;.RE/TE.v.?ERATURE LIMITATICN.......
E 3s; 7 3 3/*.7.3 COMP 0hENT COOLING WATER 5YSTEM........................
83/47-3 3/4.7.4 SALT WATER COOLING SYSTEM...~........i..................
B 3/4'7-3 l
I 3,'4. 7. 5 CthTROL RCCM EMERGENCY AIR CLEANUP SYSTEM.............
5 2,a 7-4 3 /4. 7. 6 5 N'J ! E E R S.*.................................,..,.......,...
B 3/4 7-5 3/4.7.7 SEALID SCURCE CONTAMINATION...........................
8 3/4 7-6 i
3/.4.7.8 FIRE SUPPRESSION SY5TEMS.............................'.
B 3/4 7-6 3/4.7.9 FIRE RATED ASSEMBLIES.................................
B 3/4 7-7 L
L
'/4.9 ELECTR' CAL POWER SYSTEMS 3/.3.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, DC SOURCE 5 and ONSITE POWER DISTRIBUTION SYSTEMS................
B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICE 5...............
B 3/4 8-3 3/4.9-REF'JELING OPERATIONS 3/4.9.1 20RCN CONCENTRATION...................................
8 3/4 9-1
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3/4. 9. 2.
INSTRUMENTATION.......................................
B 3/4 9-1 3/4.9.3 DECAY TIME............................................
8 3/4 9-1 3/4.9.4 CONTAINMENT PENETRAT!0NS..............................
8 3/4 9-1 3/4.9.5 COMMUNICATIONS..........,.............................
8 3/4 9-1
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' XIII AMEN 0 MENT N0.16
f***5 d*'
t ATTACHMENT TO LICENSE AMENDMENT N0. 85 FACILITY OPERATING LICENSE NO. NPF-10 j
DOCKET NO. 50-361 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
Also enclosed are the following overleaf pages to the amended pages, j
AMENDMENT PAGE-OVERLEAF PAGE 3/4 7-17 3/4 7-18 i
B 3/4 7-5 B 3/4 7-6 i
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PLANT SYSTEMS BASES 3/4.7.6 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant system and all uther 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 J
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.
For visual inspection snubbers are categorized into two (2) groups, those accessible and those inaccessible during reactor operation.
For functional testing, snubbers are categorized into types by design and manufacturer, irre-
-spective of capacity.
For example, Pacific Scientific snubbers are divided into four types corresponding to different design features:
PSA 1/4 and 1/2 are one type; PSA 1, 3, and 10 are another; PSA 6 is another; and PSA 35 and l
100 are a fourth type.
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 deter-mine the next inspection.
However, the results of such early inspections per-formed 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 i
the previous schedule.
Amendment No. 85 allows a one time extension of the l
l inspection period during Cycle 5 operation while the NRC develops generic guidance applicable to 24 month operating cycles.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shut-downs at refueling intervals.
Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the,above surveillance programs, i
SAN ONOFRE-UNIT 2 B 3/4 7-5 AMENDMENT NO. 85 8
l PLANT SYSTEMS BASES SNUBBERS (Continued)
The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and ssociated installation and maintenance records (new1. installed snubber, seal a
replaced, spring replaced, in high radiation area, i 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 statistical 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.
3/4.7.7 SEALED SOURCE CONTAMINATION
[
The limitations on removable contamination-for sources re leak testing, including a pha emitters, is based on 10 CFR 70.39(c)quirin limit for j-plutonium.
This lim tation will ensure that leakage from b roduct, source, and special nuclear material sources will not exceed allowab e intake values.
l Sealed sources are classified into three groups aci:ording 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 or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shield mechanism.
3/4.7.8 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 sprinklers, and fire hose stations.
Thecollectivecapabi1Ityofthe fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.
In the event that portions of the fire suppression systems are inoperable,' alternate backup fire fi hting equipment is required to be made available in the affected areas unti 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 alternate means of fire fi hting than if the inoperable equipment is the primary means of fire suppress on.
The surveillance requirements provide assurance that the minimum OPERABIt.ITY requirements of the fire suppression systems are met.
i SAN ONOFRE-UNIT 2 B 3/4 7-6 p
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a 4
'v-PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
No Inoperable Snubbers Subsequent Visual,,,
per Inspection Period Inspection Period
- I 0
18 months i 25%
1 12 months t 25%
2 6 months
- 25%
3,4 124 days
- 25%
5,6,7 62 days't 25%
8 or more 31-days t 25%
The snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule, c.
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, and (3) fasteners for attachment of the snubber to (a) the component or pipe and (b) 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 that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.6.e or 4.7.6.f as applicable.
However, when a 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 commor, hydraulic fluid reservoir shall be counted as inoperable snubbers.
The inspection interval shall not be lengthened more than one step at a time.
- The provisions of Specification 4.0.2 are not applicable.
- 20 months i 25% for inspections conducted during the Cycle 5 refueling j
outage.
SAN ONOFRE-UNIT 2 3/4 7-17 AMEN 0 MENT NO. 85
y PLANT SYSTEMS
.I SURVEILLANCE REQUIREMENTS (Continued) d.
Functional Tests At least once per refueling interval during shutdown, a representative sample of at least 15% 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 of a type that does not meet the functional test acceptance criteria of Specification 4.7.6.e or 4.7.6.f. an sdditional 15% 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.
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 5 feet of heavy equipment (valve, pump, turbine motor,etc.)
.)
3.
Snubbers within 10 feet of the discharge from a safety relief Snubb r that are especially difficult to remove or 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 ratested 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 ratested.
Test results of those snubbers may not be included for the re-sampling.
- Permanent or other exemptions from functional testing for individual snubbers in these caterories may be granted by the Commission only if 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.
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SAN ONOFRE-UNIT 2 3/4 7-18 AMENDMENT NO. 76 g p, iq,
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