ML20129F361
| ML20129F361 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/20/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Nebraska Public Power District (NPPD) |
| Shared Package | |
| ML20129F366 | List: |
| References | |
| TAC 56090 DPR-46-A-092, NUDOCS 8506060753 | |
| Download: ML20129F361 (10) | |
Text
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- puc oq[g UNITED STATES g
g NUCLEAR REGULATORY COMMISSION
[
WASHINGTON. D. C. 20555 5
NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 92 License No. DPR-46 1.
The Nuclear Regulatory Commission (the Commission) has' found that:
A.
The application for amendment by Nebraska Public Power District dated October 5, 1984, as supplemented, October 29, 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 app ~iication, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without er.dangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission'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.
2.
Accordingly, the licensee is amended by changes to the Technical Spec-ifications-as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:
(2) Technical Specification The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 92, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8506060753 850520 PDR ADOCK 05000298 P
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- 3.
This license amendment is effective as of its date of issuance.
FOR THE NilCLEAR REGilLATORY COMMISSION d. d _. - -
W omenic B. Vassallo,_ Chief D
Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 20,'1985
o o
1 ATTACHMENT TO LICENSE AMENDMENT N0. 92
' FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 Revise the Appendix A Technical Specifications'as follows. The revised.
areas are indicated by marginal lines.
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Remove Insert
- 116 116 137a 137a 137b 137b 137c 137c 137d 137d 137e 137e 137f through 137m 229 229 I
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LIMITING CONDITIONS FOR OP ION SURVEILLANCE REOUIREMENTS
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3.5. A *(Cont 'd. )
4.5.A. (Cont'd.)
5.
From and after the date that one 5.
When it is determined that the LPCI LPCI subsystem is made or found to subsystem is inoperable, both core be inoperable for any reason, contin-spray subsystems, the containment ued reactor operation is permissible cooling subsystem and the diesel only during the succeeding 7 days, un-generators required for operation of less it is sooner made operable, pro-such components if no external source vided that during such 7 days all of power were available shall be active components of both core spray demonstrated to be operable immediately subsystems, the containment cooling and daily thereafter, subsystems (incF; ding 2 LPCI pumps) and the diesel generators required for operation of such components shall be operable.
6.
All recirculation pump discharge 6.
All recirculation pump discharge j
valves shall be operable prior to valves shall be tested for oper-l reactor startup (or closed if ability during any period of permitted elsewhere in these Reactor cold shutdown exceeding specifications).
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if operability tests have not been performed during the preceding 31 days.
7.
The reactor shall not be str.rted up with the RHR system supplying cooling to the fuel pool.
8.
If the requirements of 3.5.A 1,2,3,4,5,6 or 7 cannot be met, an orderly shut-down of the reactor shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Containment Cooling Subsystem B.
Containment Cooling Subsystem (RHR (RHR Service Water)
Service Water) 1.
Except as specified in 3.5.B.2, 1.
Containment Cooling Subsystem Testing 3.5.B.3, and 3.5.F.3 below both con-shall be as follows:
tainment cooling subsystems loops shall be operable whenever irradiated Item Frequenev fuel is in the reactor vessel and reactor coolant temperature is great-a.
Pump & Valve Once/3 months er than 212*F, and prior to reactor Operability startup from a Cold Condition.
b.
Pump Capacity Test. After pump main-Each RER service tenance and every water booster pump 3 months shall deliver 4000 8pm.
c.
Air test on dry-Once/5 years well and torus headers and nozzles.
Amendment No jf, 92
-116-
' LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT b.6.H Shock Suppressors (Snubbers) 4.6.H Shock Suppressors (Snubbers) 1.
During all modes of operation The following surveillance require-except_ Cold Shutdown and ments apply to all snubbers as noted Refuel, all safety-related in 3.6.H.l.
snubbers shall be operable except as noted in 3.6.H.2 1.
All snubbers shall be visually l
and 3.6.H.3 below.
inspected in accordance with the following schedule:
l 2.
With one or more snubbers in-operable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> re-Number of Snubbers Next Required place or restore the inoper-
'Found Inoperable Inspection 1
able snubber (s) to OPERABLE During Inspection Interval status and perform an_engi-or During Inspection neering evaluation per Interval
]-
Specification 4.6.H.4.d on
-the supported component or 0
18 months j; 25%
declare the supported system or 1
12 months j; 25%
subsystem inoperable and follow 2
6 months j; 25%
the appropriate ACTION state-3,'4 124 days j; 25%
ment for tnat system.
5,6,7 62 days j; 25%
l 3.
If a snubber is determined to be inoperable while the reactor is The required inspection interval in the shutdown or refuel mode, shall not be lengthened more the snubber shall be made oper-than one step at a time.
able or replaced prior to reactor startup.
Snubbers may be categorized in groups, " accessible" or "inac-cessible" based on their acces-sibility for inspection during reactor operation and by type, hydraulic or mechanical. These four groups may be inspected independently according to the above schedule.
2.
Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impair-ed OPERABILITY, (2) attachments to the foundation or supporting 1
1 Amendment No. )(, JVI, 92 l37,_
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LhMITINGCONDITIONFOROPERATION SURVEILLANCE REQUIREMENT 4.6.H Shock Suppressors (Snubbers)
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(cont'd) structure are secure. Snubbers
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vhich 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 estab-lished and remedied for that particular snubber and for other snubbers that may be generically susceptible; or (2) the affected snubber is functionally tested in the as found condition and I
determined OPERABLE per Specifi-l cations 4.6.H.5 or 4.6.H.6 as l
applicable. However, when the I
fluid port af a hydraulic snubber is found to be uncovered, the i
snubber shall be determined in-I operable and cannot be determined OPERABLE via functional testing l
for the purpose of establishing the next visual inspection inter-val. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.
3.
At least once per 18 months dur-ing 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 fune-tional test acceptance criteria of Specification 4.6.H.5 or 4.6.H.6, an additional 10% of that type of snubber shall be function-ally tested.
4.
The representative sample select-ed for functional testing shall include various configuration, operating environments and the range of size and capacity of snubbers.
l Amendment No. )4F,,Ef, 92
-137b-
f.IMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMDIT
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4.6.H Shock Suppressors (Snubbers)
(cont'd)
In addition to the regular sam-l a.
ple, 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 these snubbers may not be included for the resampling.
- b. Permanent or other exemptions l
from functional testing for individual snubbers, in high radiation zones or that are difficult to remove may be granted by the Commission only if a justifiable basis for l
exemption is presented and/or snubber life destructive test-ing was performed to qualify snubber operability for all design conditions at either the completion of their fab-rication or at a subsequent date.
- c. If any snubber selected for l
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 and subject to the same defect shall be tested or inspected to determine if the defect is pre-sent. This testing requirement shall be independent of the re-quirements stated above for snub'cers not meeting the func-tional test acceptance criteria.
- d. For the snubber (s) found inoper-l able, an engineering evaluation shall be performed to determine the need for further action or testing on affected components.
Amendment No. j)(, 92
-137c-
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o LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 4.6.H Shock Suppressors (Snubbers)
(cont'd) 5.
Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional "d.
test shall verify that:
g 1.
Activation (restraining act-ion) 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.
6.
Mechanical Snubbers Functional Test Acceptance Criteria e
The mechanical snubber func-g..
tional test shall verify that:
5 a-1.
The force that initiates a
free movement of the snub-O ber rod in either tension or compression is less than f
the specified maxi:num drag force.
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2.
Activation (restraining act-
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fon) is achieved within the J.
specified range of velocity or acceleration in both j'-
tension and compression.
5 3.
Snubber release rate, where 4:
required, is within the 4
s,pecified range in com-pression or tension.
7.
Snubber Service Life Monitoring A record of the service life of cach snubber as noted in 3.6.H.1, l the date at which ebe designated service life commences, and the l
installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.4.2.J.
l AmendmentNo.J4',92
,,-137d-,
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREME.f V
4.6.H Shock Suppressors (Snubbers)
(cont'd)
Concurrent wich the first in-service visual inspection and at least cnce per 18 months thereafter,.the installation and maintenance records of each snubber noted in 3.6.H.1 l
shall be reviewed to verify that the indicated service l
life has not been exceeded or will not be exceeded prior to the next scheculed 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, replacemen: or reconditioning shall be indicated in the records.
Amendment Nos.,J(,,S1f, 92
_g37,_
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O 6.4.2.G -(esst'd)
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usage evaluation per the pME Doiler and Pressure Vessel Code Section III was performed for the conditions defined in the design specification. The locations to be monitored shall be:
a.
The feedwater nozzles b.
The shall at or near the waterline l
c.
The flange studs
(
2.
Monitoring, Recording, Evaluating, and Reporting Operational transients that occur during plant operations will, a.
at least annually, be reviewed and compared to the transient conditions defined in the component stress report for the locations listed in 1 above, and used as a basis for the existing fatigue analysis.
~b.
The number of transients which are comparable to or more severe than the transients evaluated in the stress report Code fatigue usage calculations will be recorded in an operating log book.
For those transients which are more severe, available data, such
- as the metal and fluid temperatures, pressures, flow rates, and other conditions will be recorded in the log book, The number of transient events that exceed the design specification c.
L quantity and the number of transient events with a severity greater.
i than that included in the existing Code fatigue usage calculations shall be added. When this sua exceeds the predicated number of l
2 design condition events by twenty-five, a fatigue usage evaluation of such events will be performed for the affected portion of the RCPB.
H.
Records of individual plant staff members showing qualifications, training and retraining.
I.
Records for Environmental Qualification which are covered under the pro-visions of Specification 6.3.
J.
Records of the service lives of all hydraulic and mechanical snubbers noted in 3.6.H.1, including the date at which the service life commences l-
-and associated installation and maintenance records.
6.4.3 2 Year Retention Records.and logs relating to the following items shall be kept for two years.
A.
The test results, in units of microcuries, for leak tests of sources performed pursuant to Specification 3.8.A.
B.-
Records of annual physical inventories verifying accountability of the sources on record.
L 1.
See paragraph N-415.2. ASME Section III, 1965 Edition.
2.
The Code rules permit exclusion of twenty-five (25) stress cycles _ from secondary stress ani fatigue usage evaluation.
(See paragraphs N-412(c)(3) and N-417.10(f) of the Susmer 1968 Addenda to ASME Section III, 1968 Edition.)
Ame' dment No.)(, #f, 92
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