ML20126F174

Amend 92 to License DPR-59,revising Tech Specs Re Operability & Surveillance Requirements for Hydraulic & Mechanical Snubbers

ML20126F174
Person / Time
Site:	FitzPatrick
Issue date:	05/29/1985
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Power Authority of the State of New York
Shared Package
ML20126F178	List: ML20126F174 ML20126F187
References
DPR-59-A-092 NUDOCS 8506170383
Download: ML20126F174 (14)

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UNITED STATES y

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NUCLEAR REGULATORY COMMISSION L

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POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENCMENT TO FACILITY OPERATIhG LICENSE Arendment No. 92 License No. DPR-59 i

1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by the Power Authority of the State of New York (the licensee) dated July 13, 1981, as supplemented i

May 3, 1984. July 27, 1984 and January 18, 1985, complies with j

the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; i

B.

The facility will operate in confomity with the application,

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the provisions of the Act, and the rules and regulations of the Comission; 4

i C.

There is reasonable assurance (1) that the activities authorized 4

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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the corron defense and security or to the health and safety of the public; and i

E.

The issuance of this amendirent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachrent to this license amendment and paragraph 2.C(2) of Facility Operating License No.

OPR-59 is hereby amended to read as follows:

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i 2-(2) Technical Specifications 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.

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This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION j

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r Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing i

Attachment:

Changes to the Technical Specifications Date of Issuance: ffay 29,1985 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 92 1

FACILITY OPERATING LICENSE NO. OPR-59 DOCKET NO. 50-333 Revise the Appendix "A" Technical Specifications as follows:

Remove Insert vi vi 145a 145a 145b 145b 145c l

145d 145e 145f 145g 156 156 156a 156a 255 255 t

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LIST OF TABLES (CONT'D)

Table Title E*SS 3.6-1 safety Related Shock suppressors (Snubbers) 156b I Delett 4.6-1 Comparison of the James A. FitsPatrick Nuclear 157 Power Plant Inservice Inspection Program to ASME Inservice Inspection Code Requirements 3.7-1 Process Pipeline Penetrating Primary containment 198 4.7-1 Minimum Test and Calibration Frequency for 210 containment Monitoring systems 4.7-2 Exception to Type C Tests 211 6.10-1 Component cyclic or Transient Limits 261 6.11-1 Protection Factors for Respirators 4

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Amendment No. Ad, y/, 92 vi f

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IINITINC CONDITION FOR OPERATION SURVEILI.ANCE REOUIREMENT 3.6 (cont'd) 4,6 (cont'd) 3.6.1 Shock Suppressors (Saubbers) 4.6.I Shock Suppressors (Snubbers)

Applicability t

Appilcability i

Applies to the operational status of the shock suppressors (saubbers),

Applies to the periodic testing requirement for the shock suppressors Objective (saubbers).

objective To assure the capability of the snubbers to:

To assure the operability of the snubbers Prevent unrestrataed pipe motion to perform their latended functions.

i under dynamic loads as might occur Specification daries an earthquake or severe transient, and Each snubber shall be demonstrated Allow normal thermal motion during operable by performance of the following startup and shutdown.

augmented inservice laspection program.

1.

I Speelfleetica Snubbers shall be visually laspected in accordance with the following schedule:

1.

Durlag all modes of operation except Cold shutdown and Refueltag, all No. Inoperable Snubbers Subsequent Visual i

sambbers which are required to per Inspection Period Inspectica period *#

protect the primary coolant system or any other safety related system 0

i or component shall be operable.

18 months i 25%

1 During Cold Shutdown or Refueltog 12 months 1 25%

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mode of operetton, only those 6 months i 25%

3.4 124 days 1 25%

snubbers shall be cperable which are 5.6.7 62 days i 25%

on systees that are required to be 8 or sere 31 days 1 25%

cperable la these states.

2.

With one or more snubbers The inspection interval may not be laoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during extended more than one step at a Line.

normal operation, or withia 7 days Amendment No. )Mr. 92 145a t

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3.6 (cent'd) 4.6 (coat'd) declas Cold Shetdeum or Refueltag s The snubbers may be categorized into two l

mode of operetlom for systems which groups: Those accessible and those j

are regelred to be operable la inaccessible ductas reactor operation.

1 these modes, complete gag,of the Each group may be laspected

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felleerlag:

ladpendently la accordance with the above schedule.

s. replace er restore the looperable snubber (s) to operable 2.

Visual laspection shall verify (1) i status er.

that there are no visible

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ladications of damage or impaired

b. declare the supported system OPERABILITY (2) attachments to the laeperable and follow the foundattom or supportlag structure i

appropriate limiting condition for are secure, and (3) la those operatien statemoet for that locations where sembber movements system, er.

can be manu11y induced without discosaecting the sambber, that the i

c. peeform an engineering snubber has freedom of movement and evaluettee to demonstrate the is not frosea sp.

Saubbers which looperable sembber is unnecessary appear Laoperable as a result of i

to assere operabiltly of the system visual inspections may be determined i

er to meet the desiga criteria of OpsRABLE for the purpose of l

the system, ggd remove the sambber establishlag the most visual frem the system.

Inspection interval, providtag that (1) the ca'use of the rejectica is i

3.

Eftth ese er more sembbers found clearly established and remedied looperable, withia 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> perform for that particular sembber and for a visual laspectice of the other snubbers that may be generically sepperted compeeest(s) asseclated susceptible; and (2) the affected sembber with the laeperable soebber(s) and is functionally tested la the as found docummet the results. For all condition and deterstaed opgEASLs per i

modes of operaties sacept Cold specifications 4.6.I.7 or 4.6.I.S. as sketdown and Befueltas, within 14 applicable. Eydraulic sembbers which days complete an engineering have lost sufficient fluid to potentially

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evaleottee as per speelfication cause uncoverlag of the fluid 4.6.I.6 to essere that the reservoir-to-sambber valve assembly laoperable sambber(s) has not port or bottaming of the adversely affected the supported composest(e). For Cold 3butdeum or asteellap mode, this evaluation shall be completed within 30 days.

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l 4.6 (cont'd) fluid reservoir piston with the snubber in the fully extended position shall be functionally tested to determine operability.

3.

Once each operating cycle 10% of each type of snubbers shall be 4

functionally tested for operability, either in place or in a bench test.

For each unit and subsequent unit that does not meet the requirements of 4.6.I.7 or 4.6.I.S. an additional l

10% of that type of snubber shall be functionally tested until no more 1

failures are found, or all units have been tested.

4.

The representative sample selected for functionally testing shall

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include the vaelous configurations, operating environments and the range 1

of size and capacity of snubbers.

1 At least 25% of the snubbers in the

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representative semple shall include snubbers from the following three

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categories:

I a.

The first snubber away from reactor vessel nozzle.

b.

Snubbers within 5 feet of heavy h

equipment (valve, pump, turbine, j

motor, etc.).

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Snubbers within 10 feet of the i

discharge from a safety relief j

valve.

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amendment No. 92 145c

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4.6 (cont'd) i In addition to the regular sample, snubbers which failed the previous functional test shall be. retested during the neat test period.

If a i

space snubber has been l'asta11ed in 4

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 i

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ratested. Test results of these snubbers may not be included for the re-sampling.

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If any snubber selected for l

functional testing either fails to i

lockup or falls to move, i.e.,

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frozen in place, the cause will be i

evaluated and if due to manufacturer j

or design deficiency, snubbers of the same design subject to the same l

defect shall be functionally tested.

This testing requirement shall be ladopendent of the requirements I

stated above for snubbers not meeting I

the functional test acceptance criteria.

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6.

For the snubber (s) found inoperable, an engineering evaluation shall be

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supported by the snubber (s).

The purpose of this engineering evaluation shall be to determine if the components supported by the l

snubber (s) were adversely affected by i

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the inoperability of the snubber (s) in order to ensure that the supported components remain capable of meeting the designed service requirements.

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4.6 (cont'd) 7.

The hydraulle snubber functional test shall verify that Activation (restralning action) s.

is achieved within the specified range of velocity or acceleration in both tension and compression.

b.

Snubber bleed, or release rate, where required. is within the speelfled rense 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 bs vertfled.

S.

The mechanical snubber functional test shall verify that a.

The force that inttlates free movement of the snubber rod in either tension or compression is less than the speelfled mastnum drag force. Drag force shall not have lacreased more than 50 % since the it

• 1nctional

test, b.

Activation (restralning action) is achieved within the specified range of velocity or acceleration in both tension and compression.

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4.6 (cont'd)

Snubber release rate, where c.

required, is within the speelfled range la compression or tension. For enubbers speeltically required not to l

displace under continuous load, j

the ab!!!ty of the snubber to I

withstand load without displacement shall be vertfled.

9.

snubber service Life Monitoring A record of the service life of each j

snubber, whose failure could adversely affect the primary coolant i

i or other safety-related system, the date at which the designated service i

life commences, and the installation and maintenance records on which the designated service life is based 1

shall be maintained as required by specification 6.10.3.13.

8 At least once per operating cycle, the installation and maintenance records for each snubber, whose failure could adversely affect the i

primary coolant or other safety related system, shall be reviewed to j

verify that the indicated service life has not been exceeded or will i

not be escoeded prior to the neat scheduled snubber service life revlow.

If the Indicated service j

life will be escoeded pelor to the next scheduled snubber service life i

review, the snubber service life shall be reevaluated or the snubber i

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92 14SI

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4.'6 (cont'd) shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service 3ife c'eview. This reevaluation, replacement or reconditioning s?.all be indicated in the records.

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i 3.6 and 4.6 BA3gs (Cont'd) l events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (for normal et i 10 percent and i 15 percent of tne operation) or 7 days (for cold shutdown or j

average speed for the above and below 80 refueltag mode of operation) is allowed for j

percent power cases, respectively. If the repairs or replacement of the snubber prior reactor is operettaa on one pump, the loop to taking any other action. Following the 3

select logic trips that pump before maklag 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (or 7 day) period, the, supported j

the toep selection, system must be declared inoperable and the Limiting Condittom of Operation statement seguiring the discharge valve of the lower for the supported system followed. As an i

speed loop to reesta closed until the speed alternative to enubber repale or replacement of the faster pump is below 50 percent of an enslueering evaluation may be performed:

l Its rated speed provides assurance when to demonstrate that the inoperable snubber j

going from one to two pump operation that is unnecessary to assure operability of the escesolve vibration of the jet pump risere system or to meet the deelga criteria of the i

will not occur.

system; and, to remove the sambber from the system. With one or more saubbers found j

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shock susecessors inoperable, withia 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> a visual inspection shall be performed on the 1

Snubbers are designed to prevent supported component (s) associated with the f

unrestralmed pipe mottom under dynamic loads inoperable snubber (s) and the results shall i

as alght occur during as earthquake or be documented. For all modes of operstlos i

severe treastent, while allowing normal except Cold shutdown and Refueling, within t

I thermal motion during startup and shutdc,wn.

14 days an englooeging evaluation shall be l

The consequences of as inoperable snubber is performed to ensure that the inoperable as lacrease in the probability of structural snubber (s) has not adversely affected the 3

damage to piping as a result of a selselc or supported component (s).

For Cold shutdown j

other event tattlettag dynamic loads. It is or Refuellas mode, this evaluation shall be therefore regelred that all snubbers completed within 30 days. A period of 7

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required to protect the primary coolant days has been selected for repair or f

system or any other safety system or replacement of the inoperable enubber during camponeet be operable during reactor cold shutdown or refuellas mode of operation l

l operettee. Seebbers escluded from this because la these modes the relative l

i inspectlen program are those lastelled on probability of structural damage to the l

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non-eafety related systems and them only if piping systems would be lower due to lower their fattere or failure of the system on values of total stresses on the piping 3

which they are lasta11ed would have no systems.

In case a shutdown is required, adverse effect on any safety-related the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a cold l

system. Because the sambber protection is shutdown condition will permit an orderly I

required only during low probability shutdown consistent with standard operating procedures.

Amendment No. #. 92 156 l

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3.6 and 4.6 34s33 (Cost'd)

The visual laepection fregeeney is based upon maintaining a coastsat level of sam m e To provide assursace of snubber functional i

protecties to systems. Therefore, the reliability, a representative sample of the required laspectlon laterval varies lastalled saubbers will be functionally tested

! aversely with the observed snubber failures duetag each operating cycle. Selectica of a and is deterslaed by the number of representative sample of 10% of es*ch type of laeperable saubbers found during as safety related snubbers provides a confidence laspection. Inspections performed before level within acceptable limits that these j

that laterval has elapsed may be used as a supports will be la en operable condittoa.

j new reference point to deterales the mest observed fa11eres of these sample snubbers j

Neuever, the results of such shall require functional testlag of addittomal laspection.

early taspection performed before the units.

l ortglaal required time laterval has elapsed (nominal time less 251) may not be used to Hydraulic snubbers and mechanical saubbers may 1

lengthem the required laspection laterval, each be treated as a different entity for the j

.,,as,ecuon ub... r..uits e.guir. a above surveillance programs.

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shorter inspection laterval will override the previous sabedule. When the cause of The service life of a anubber is evaluated i

the rejection of a snubber is clearly uslag manufacturer laput and information and l

established and remedied for that sambber also through consideration of the installation

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and for any other sambbers that may be and maintenance records (newly lasta11ed 3enerically susceptible, and v.-ified by snubber, seal replaced, spelag replaced, la laservice functional testing, that saubber high radiatlos area, la high temperature area, etc...).

may be esempted from belas coasted as The requirement to monitor the inoperable. Geeerically susceptible snubber service life is included to ensure that snubbers are these which are of a specific the snubbers periodically undergo a performance make or model that have the same destga evaluation in view of their age and operattas features directly related to rejection of conditions. These records will provide i

j the snubber by visual laspection, sad are statistical bases for future consideration of stellarly located or esposed to the sees sam m e service life. The requirements for the

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environmental conditions such as malatenance of records and the saubber service j

temperature, radiatloa, sad vibration.

life review are not latended to affect plant When a saubber is found laoperable, an operation.

englaeerlag evaluatlea is performed. La addition to the determination of the snubber made of failure, la order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber.

The engineering evaluation i

j shall deteralee whether or met the sembber mode of failure has leparted a sigalficant effect or degradattom on the supported compement or system.

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l (B) The following recoros shall be retained for the duration of the Facility Operating License:

1.

Records of any drawing changes reflecting facility design

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modifications made to systems and equipment described in the Final

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Safety Analysis Report.

2.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

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3.

Records of facility radiation and contamination surveys.

4.

Records of radiation exposure for all individuals entering radiation j

control areas.

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Records of gaseous and liquid radioactive material released to the 1

environs.

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Records of transient or operational cycles for those facility components identified in Table 6.10-1.

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Records of training and qualification for current members of the plant staff.

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8.

Records of in-service inspections performed pursuant to these Technical specifications, j

9.

Records of Quality Assurance activities required by the Quality Assurance Manual.

10. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

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11. Records of meetings of the PORC and the SRC.

12. Records for Environmental Qualification which are covered under the provisions of paragraph 6.15.

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13. Records of the service Jife of all hydraulic and mechanical snubbers, L

whose failure could adversely affect any safety-related system,

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including the date at which the service life commences and associated installation and maintenance records as of the effective date of this l

j ammendment.

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6.11 RADIATION PROTECT!0P PROGRAM i

4 Procedures for personnel radiation protection shall be prepared and j

adhered to for all plant operations.

These procedures shall be formulated to maintain radiation esposures received durin ' operation and maintenance as far below the limits specified in 10 CFR 2 as 1

practicable.

The procedures shall include plannin training for operation and maintenance activities.g, preparation, and i

They shall also include exposure allocation, radiation and contamination control e

j techniques, and final debriefing.

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Amendment No. Jf, g. 92 1.

Order dated October 24, 1980 255 1

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