ML17157A740
| ML17157A740 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/28/1991 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17157A741 | List: |
| References | |
| NUDOCS 9107170274 | |
| Download: ML17157A740 (26) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 PENNSYLVANIA POWER
& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUSgUEHANNA STEAM ELECTRIC STATION UNIT 1 AMENDI1ENT TO FACILITY OPERATING LICENSE Amendment No.
113 License No.
NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power Light Company, dated April 12, 1991 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),'nd the Commission's 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 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 set forth in 10 CFP, Chapter I; 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 license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No.
NPF-14 is hereby amended to read as follows:
(2) ~ti 1S if' dE The Technical Specifications contained in Appendix A, as revised through Amendment I'Io.
113 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
~~07170n4 9~06zs PDR ADGCK 05000387 PDR
I 1
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 28, 1991 Halter R. Butler, Director Project Directorate I-2 Division of Reactor Projects - I/II
'I 4
I
ATTACHMENT TO LICENSE AMENDMENT NO 113 FACILITY OPERATING LICENSE NO.
NPF-14 DOCKET NO. 50-387 RENOVE Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The overleaf pages are provided to maintain document completeness."
INSERT 3/4 7-9 3/4 7-10 3/4 7-11 3/4 ?-12 3/4 7-13 3/4 7-14 B 3/4 7-1 B 3/4 7-2 3/4 7-9*
3/4'7-10 3/4 7-10a 3/4 7-10b 3/4 7-11 3/4 7-12 3/4 7-13 3/4 7-14*
B 3/4 7-1*
B 3/4 7-2
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued C.
At least once per 18 months by:
I.
Performing a system functional test which includes simulated automatic actuation and restart and verifying that each automatic valve in the flow path actuates to its correct position, but may exclude actual injection of coolant into the reactor vessel.
3.
Verifying that the'system will develop a flow of greater than or equal to 600 gpm in the test flow path when steam is supplied to the turbine at a pressure of 150, + 15, -0 psig."
Verifying that the suction for the RCIC system is automatically transferred from the condensate storage tank to the suppression pool on a condensate storage tank water level-low signal.
d.
4.
Performing a CHANNEL CALIBRATION of the condensate transfer pump discharge low pressure alarm instrumentation and verifying.
tha lew pressure alera setpo3nt'te ha greater than er equal ts
') t 113 psig.
In the event the RCIC system is actuated and injects water into the reactor coolant system, a Special Report shall be prepared and sub-mitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
The current value of the usage factor for each affected injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
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surveillance is performed,within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the tests.
SUS/UEHANNA - UNIT 1 3/4 7-9 Amendment No. 36
474 NDITI N R
PERAYI N 3.7.4 Allsnubbers shall be OPERABLE.
0 CONDITIONS 4 and 5 for snubbers located on systems required, OPERABLE in those OPERATIONAL CONDITIONS.
~A+~:
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 4.7.4.d on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
RVEILLAN E RE UIREMENTS 4.7.4 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
As used in this specification, "type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.
b.
Snubbers are categorized as inaccessible or accessible during reactor operation.
Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7.4-1.
The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7.4-1.
C.
i ri r'isual inspections shall verify that (1) the snubber has no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable 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 irrespective of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specification 4.7.4e.
A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber. Ifcontinued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.
SUSQUEHANNA - UNIT 1 3/4 7-10 Amendment No. it/; '113
RVEILLAN E RE IREMENT n in TABLE-4,7.4-1.', ';
SNUBBER VISUALINSPECTION~INTERVAX..-'
BL B
- ,,Pop'ulation';:::.':::,::,:;:
Column A:;;.",;:.-.,;,::,',::::;:,",:.Column B:::~;:.;.:;:;:.; ',:;
Column"C:."".':;o'r'Category
. Extend Interval.:,,;:Repeat Interval'".-j,,::.; Reduce Tri'erv'al "
(Notes 1: & 2)':=,:.,
(Notes 3 & 6)'.:+.:,;;:-,,(Notes'.4
&'6),:":-;:.';:.':,:.:.(Notes 5 &6)'::
'0 0
0 0
0 0
150 0
12 13 25 750 1,000 or greater 12 20 29 18 56 36 48 78 Note 1:
The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These categories may be examined separately or jointly. However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
Note 2:
Interpolation between population or category sizes and the number of unacceptable snubbers is permissible.
Use next lower integer for the value of the limit for Columns A, 3, or C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
Note 3:
Ifthe number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.
SUSQUEHANNA - UNIT 1 3/4 7-10a Amendment No.
113
RVEIL A E RE IREMENT n in Note 4:
Ifthe number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
Note 5:
If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, ifthe number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.
Note 6:
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
SUSQUEHANNA - UNlT 1 3/4 7-10b Amendment No.
113
RVEILLAN E RE UIREMENT n in 1
n During the first refueling shutdown and at least once per 18 months thereafter during shutdown, a representative sample of at least that number of snubbers which follows the expression 35 (1 + 2 ) where c = 4, is the allowable number of snubbers not meeting the acceptance criteria selected by the operator, shall be functionally tested either in-place or in a bench test.
For each number of snubbers above c which does not meet the functional test acceptance criteria of Specifications 4.7.4.ena p additional sample selected according to the expression 35 (l + 3) ( c + t )'a - c) shall be functionally tested, where a is the total number of snubbers found inoperable during the functional testing of the representative sample.
Functional testing shall continue according to the expression b [35 (l + 3 ) ( c + t )'l where b is the number of snubbers found inoperable in the previous re-sample, until no additional inoperable snubbers are found within a sample or until all snubbers 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 followingthree categories:
1.
The first snubber away from each reactor vessel nozzle.
2.
Each snubber within 5 feet of heavy equipment, valve, pump, turbine, motor, etc.
3.
Each snubber within 10 feet of the discharge from a safety relief valve.
SUSQUEHANNA - UNIT 1 3/4 7-11 Amendment No. 68, 113
RVEILLAN E RE IREMENT n in 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.
Ifany snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause willbe evaluated and ifcaused 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 any 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 snubber(s) in order to ensure that the supported component remains capable of meeting the designed service.
e.
n The mechanical snubber functional test shall verify that:
1.
The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.
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.
SUSQUEHANNA - UNIT 1 3/4 7-12 Amendment No. 67, 113
PLA Y
RVEILLAN E RE IREMENT C ntinu
- t. Pg.g jj<wll~ ) j rvi L'f i r' 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.
Concurrent with the first inservice visual inspection and at least once per 18 months 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 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.
SUSQUEHANNA - UNIT 1 3/4 7-13 Amendment No. 68, 113
3/4. 7. 5 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.5 Each sea1ed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination.
APPLICABILITY: At al 1 times.
ACTION:
a r With a sealed source having removable contamination in excess of the above limit,'ithdraw the sealed source from use and either:
l.
Decontaminate and repair the sealed
- source, or b.
2.
Dispose of the sealed source in accordance with Commission Regulations.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE UIREMENTS 4.1.5.1 ~TR 1
-5 1
4 4 lid <<4 and/or contam>nation by:
a.
The licensee, or b.
Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0..905 microcurie per test sample.
4.7.5.2 Test Fre uencies - Each category of sealed
- sources, excluding startup sources and f ssion detectors previously subjected to core flux, shall be tested at the frequency described below.
a.
Sources in use - At least once per six months for all sealed sources
~d 1.
With a half-life greater than 30 days, excluding Hydrogen 3
(tritium), and 2.
In any form other than gas.
SUSQUEHANNA - UNIT 1 3/4 7-14 Amendment No.
78
3/4.7 PLANT SYSTEMS BASES 3/4,7.1 SERYICE WATER SYSTEMS The OPERABILITY of the service water systems ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.
The redundant cooling capacity of these
- systems, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.
3/4.7.2 CONTROL ROOM EMERGENCY OUTSIDE AIR"SUPPLY SYSTEM The OPERABILITY of the control room emergency outside air supply system ensures that the control room will remain habitable for operations persohhel during and following all design basis accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to S rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A", 10 CFR Part 50.
Cumulative operation of the system with the heaters OPERABLE for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPT filters.
3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM The reactor core isolation cooling (RCIC) system is provided to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without requiring actuation of any of the Emergency Core Cooling System equipment.
The RCIC system is conservatively required to be OPERABLE whenever reactor pressure exceeds 150 psig.
This pressure is substantially below that for which the RCIC system can provide adequate core cooling for events requiring the RCIC system.
The RCIC system specifications are applicable during OPERATIONAL CONDITIONS 1, 2 and 3 when reactor vessel pressure exceeds 150 psig because RCIC is the primary non"ECCS source of emergency core cooling when the reactor is pressurized.
With the RCIC system inoperable, adequate core cooling is assured by the OPERABILITY of the HPCI system arid justifies the specified 14 day out-of-service period.
~
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The surveillance requirements provide adequate assurance that RCIC will be OPERABLE when required.
Although all active components are testable and full flow can be demonstrated by recirculation during reactor operation, a
complete functional test requires reactor shutdown.
The pump discharge piping is maintained full to prevent water hammer damage and to start cooling at the earliest possible moment.
I SUSQUEHANNA - UNIT 1 B 3/4 7"1 Amendment No.
36
P A
BAS 474 All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other 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 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.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
Therefore, the required inspection internal varies inversely with the observed snubber failure and is determined by the number of inoperable snubbers found during an inspection.
Specifically, Generic Letter 90-09 provides a
method for determining the next interval for the visual inspection of snubbers based upon the number of unacceptable snubbers found during the previous inspection, the total population or category size for each snubber type, and the previous inspection interval.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the 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 inservice functional testing, that snubber may be exempted from being counted as inoperable.
Generically susceptible snubbers are those snubbers 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.
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 further 'assurance of snubber reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals.
Selection of a representative sample according to the expression 35 (I + > ) provides a confidence level of approximately 95% that 90% to 100% of the snubbers in the plant will be OPERABLE within acceptance limits.
Observed failures of these sample snubbers willrequire functional testing of additional units.
Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
SUSQUEHANNA - UNIT 1 B 3/4 7-2 Amendment No. 86, 113
22
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 PENNSYLVANIA POWER
& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUSgUEHANNA STEAM ELECTRIC STATION Ul'IIT 2, AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
82 License No. NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power Light Company, dated April 12, 1991 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),.
and the Commission's 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 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 set forth in 10 CFR Chapter I; 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 license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-22 is hereby amended to read as follows:
Idj ~hi 222 2
2 The Technical Specifications contained in Appendix A, as revised through Amendment No.
82 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
I
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I 3.
This license amendment is effective as, of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 28,
].99].
Malter R. Butler, Director Project Directorate I-2 Division of Reactor Projects - I/II
ATTACHMENT TO LICENSE AMENDMENT NO.
82 FACILITY OPEPATING LICENSE NO.
NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The overleaf pages-are provided to maintain document completeness.*
REMO'YE 3/4 7-9 3/4 7-10 3/4 7-11 3/4 7-12 B 3/4 7-1 B 3/4 7-2 INSERT 3/4 7-9*
3/4 7-10 3/4 7-11 3/4 7-lla 3/4 7-11b 3/4 7-12*
B 3/4 7-1*
B 3/4 7-2
PLANT SYSTEMS SURVEIL'LANCE RE UIREMENTS Continued c.
At least once per 18 months by:
1.
Performing a system functional test which includes simulated automatic actuation and restart and verifying that each automatic valve in the flow path actuates to its correct, position, but may exclude actual injection of coolant into the reactor vessel.
d.
2.¹ Verifying that the system will develop a flow of greater than or equal to 600 gpm in the test flow path when steam is supplied to the turbine at a pressure of 150,
+ 15, -0 psig. "
3.
Verifying that the suction for the RCIC system is automatically transferred from the condensate storage tank to the suppression pool on a condensate storage tank water level-low signal.
4.
Performing a
CHANNEL CALIBRATION of the condensate transfer pump" discharge low pressure alarm instrumentation and verifying the low pressure alarm setpoint to be greater than or equal to 113" psig.
In the event the RCIC system is actuated and injects water into the reactor coolant system, a Special Report shall be prepared and sub-mitted to the Commission pursuant to Specification
- 6. 9. 2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
The current value of the usage factor. for each affected injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
"The provisions of Sp'ecification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the tests.
¹For the startup following the Third Refueling and Inspection Outage, this surveillance shall read as follows:
Verifying that the system will develop a flow of greater than or equal to 530 gpm with a test line pressure of 480 psig in the test flow path when steam is supplied to the turbine at a pressure of 150,
+15, -0 psig."
SUS(UEHANNA " UNIT 2 3!4 7-9 Amendment No. 62 DEC 18 f989.
474 B
LIMITIN NDITI N F R
PERATI N 3.7.4 Allsnubbers shall be OPERABLE.
0 0
CO ITID S,
- 3. 0 CONDITIONS 4 and 5 for snubbers located on systems required OPERABLE in those OPERATIONAL CONDITIONS.
With one or more snubbers inoperable, on any system, 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 4.7.4g on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
RVEILLAN E RE IREMENT 4.7.4 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0,5.
aO As used in this specification, "type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.
Snubbers are categorized as inaccessible or accessible during reactor operation, Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7.4.-1.
The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7.4.-1.
SUSQUEHANNA - UNIT 2 3/4 7-10 Amendment No.
82
PLA RVEILLAN E RE UIREMENT ntinu c.
Vi I
cinA n
ri ri Visual inspections shall verify (1) the snubber has no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are functional.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable 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 irrespective of type on that system that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specifications 4.7.4f.
A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber.
If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.
d.
i Even In i
An inspection shall be performed of all snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems within 6 months following such an event.
In addition to satisfying the visual inspection acceptance criteria, freedomwf-motion of mechanical snubbers shall be verified using at least one of the following:
(1) manually induced snubber movement; or (2) evaluation of in-place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.
SUSQUEHANNA - UNIT2 3/4 7-11 Amendment No.
82
P RVEILLAN E RE IREMENT ntin
'V SNUB
(
', Popu1ation-'..".'-, '.
,'!'r Categ'ory'.""
(Notes" 1-8c 2}'."',,'.
0 TABLE4.7.4-"1.
BER VISUAL'INSPECTION'IN'IXRVAL':,::,
F
'B BE Column A, ': '. Column B':::-',.::,.',:-'-.Column C'-
Extend Interval':
- Repeat Interval'.';..:-,Reduce=Interva1 ;
- (Notes 3 & 6),:.:,;,(Notes 4 & 6);:.:;:,,.,': '.. (Notes 5 &6)::'.','.
80 0
0 150 0
12 13 25 750 1,000 or greater 12 20 29 18 24 56 48 78 Note 1:
The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These categories may be examined separately or jointly. However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
Note 2:
Interpolation between population or category sizes and the number of unacceptable snubbers is permissible.
Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
Note 3:
Ifthe number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.
SUSQUEHANNA - UNIT 2 3/4 7-11a Amendment No.
8p
PLA l0 RVEILLAN E RE IREMENT n inu Note 4:
lV 1'l i 1 Ifthe number of unacceptable snubbers is equal't'o or less. than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
Note 5:
If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, ifthe number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.
Note 6t The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
SUSQUEHANNA - UNIT 2 3/4 7-11b Amendment No 82
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued e.
Functio'nal Tests Ouring the first refueling shutdown and at least once per 18 months thereafter during shutdown, a representative sample of snubbers shall be tested using one of the following sample plans for each type of snubber.
The sample plan shall be selected prior to the test period and cannot be changed during the test period.
The NRC Regional Admin-istrator shall be notified in writing of the sample plan selected prior to the test period or the sample plan used in the prior test period shall be implemented:
1)
At least lOX of the total of each type of snubber shall be func-tionally tested either in-place or in a bench test.
For each snubber of a type that does not meet the functional test accept-ance criteria of Specification
- 4. 7. 4f., an additional 10K 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; or 2)
A representative sample of each type of snubber shall be func-',
tionally tested in accordance with Figure 4.7.4-1.
"C" is the total number of snubbers of a type found not meeting the accep-tance requirements of Specification 4.7.4f.
The cumulative number of snubbers of a type tested is denoted by "N".
At the end of each day's testing, the new values of "N" and "C" (pre-vious day's total plus current day's increments) shall be plotted on Figure 4.7.4-1.
If at any time the point plotted falls in the "Reject" region all snubbers of that type shall be functiona11y tested.
If at any time the point plotted falls in the "Accept" region, testing of snubbers of that type may be terminated.
@hen the point plotted lies in the "Continue Test-ing" region, additional snubbers of that type shall be tested until the point falls in the "Accept" region or the "Reject" region, or all the snubbers of that type have been tested.
Test-ing equipment failure during functional testing may invalidate that day's testing and allow that day's testing to resume anew at a later time, providing all snubbers tested with the failed equipment during the day of equipment failure are retested; or 3)
An initial representative sample of 55 snubbers of each type shall be functionally tested.
For each snubber.type which does not meet the functional test acceptance criteria, another sample of at least one-half the size of the initial sample shall be tested until the total number tested is equal to the initial sample size multiplied by the factor, 1 + C/2, where "C" is the number of snubbers found which do not meet the functional test acceptance criteria.
The results from this sample plan shall be plotted using an "Accept'ine which follows the equation N =
55(1 + C/2).
Each snubber point should be plotted as soon as the snubber is tested.
If the point plotted falls on or below the "Accept" line, testing of that type of snubber may be termi-nated.
If the point plotted falls above the "Accept" line, test-ing must'ontinue until the point falls in the "Accept" region or all the snubbers.of that type have been tested.,
, SUSQUEHANNA - UNIT 2 3/4 7-12
3/4.7 PLANT SYSTEMS BASES 3/4.7. 1 SERVICE WATER SYSTEMS The OPERABILITY of the service water systems ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.
The redundant cooling capacity of these systems assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.
3/4.7.2 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY SYSTEM The OPERABILITY of the contro1 room emergency outside air supply system ensures that the control room will remain habitable for operations personnel during and following all design basis accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rems or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A, 10 CFR Part 50.
Cumulative operation of the system with the heaters OPERABLE for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31-day period is sufficient to reduce the bui ldup of moisture on the adsorbers and HEPA filters.
3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM The reactor core isolation cooling (RCIC) system is provided to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without requiring actuation of any of the Emergency Core Cooling System equipment.
The RCIC system is conservatively required to be OPERABLE whenever reactor pressure exceeds 150 psig.
This pressure is substantially below that for which the RCIC system can provide adequate core cooling for events requiring the RCIC system.
The RCIC system specifications are appIicable during OPERATIONAL CONDITIONS 1, 2, and 3 when reactor vessel pressure exceeds 150 psig because RCIC is the primary non-ECCS source of emergency core cooling when the reactor is pressurized.
With the RCIC system inoperable, adequate core cooling is. assured by the OPERABILITY of the HPCI system and justifies the specified 14 day out-of-service period.
The surveillance requirements provide adequate assurance that RCIC will be OPERABLE when required.
Although all active components are testable and full flow can be demonstrated by recirculation during reactor operation, a
complete functional test requires reactor shutdown.
The pump discharge piping is maintained full to prevent water hammer damage and to start cooling at the earliest possible moment.
SUSQUEHANNA - UNIT 2 B 3/4 7-1
BA 47 BB All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other 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 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.
Snubbers are classified and grouped by design and manufacturer but not by size.
For
- example, mechanical snubbers utilizing the same design features of the 2-kip, 10-kip, and 100-kip capacity manufactured by Company "A" are of the same type.
The same design mechanical snubbers manufactured by Company "B" for the purposes of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer.
A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50.
The accessibility of each snubber shall be determined and approved by the Plant Operations Review Committee.
The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g.,
temperature, atmosphere, location, etc.),
and the recommendations of Regulatory Guides 8.8 and 8.10. The addition or deletion of any snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
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.
Specifically, Generic Letter 9&8 provides a method for determining the next interval for the visual inspection of snubbers based upon the number of unacceptable snubbers found during the previous inspection, the total population or category size for each snubber type, and the previous inspection interval.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the 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 required a shorter inspection interval will override the previous schedule.
The acceptance criteria are to be used in the visual inspection to determine OPERABILITYof the snubbers.
SUSQUEHANNA - UNIT 2 B 3/4 7-2 Amendment No.
82