ML20245L185

Amends 93 & 68 to Licenses DPR-70 & DPR-75,respectively, Eliminating Snubber Tables from Tech Specs

ML20245L185
Person / Time
Site:	Salem
Issue date:	05/01/1989
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245L187	List: ML20245L185 ML20245L192
References
NUDOCS 8905050310
Download: ML20245L185 (29)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION e

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WASHINGTON, D. C. 20666

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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE _

Amendment No. 93 License No. DPR-70 1.

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

A.

The application for amendment filed by the Public Service Electric &

Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated April 14, 1987 as supplemented by letter dated October 5, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as ac: ended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confodnity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 (11) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon 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 Comission'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 Facility Operating License No. OPR-70 is hereby amended to read as follows:

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' (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

93, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION 4

Mohan C. Thadani for Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: May 1, 1989 9

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-2 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

93, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II 1

Attachment-Changes to the Technical l

Specifications l

Date of Issuance: May 1, 1989 i

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ATTACHMENT TO LICENSE A14ENDNENT NO. 93 FACILITY OPERATING LICENSE NO. OPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 7-28 3/4 7-28 3/4 7-29 3/4 7-29 3/4 7-30 3/4 7-30 3/4 7-31 3/4 7-31 3/4 7-32 3/4 7-32 3/4 7-32a 3/4 7-32b l

3/4 7-33 3/4 7-33 3/4 7-33a 3/4 7-33b 3/4 7-33c 3/4 7-33d 3/4 7-33e 3/4 7-33f 3/4 7-339 3/4 7-33h 3/4 7-331 3/4 7-33j 3/4 7-33k 3/4 7-331 3/4 7-33m

. ATTACHMENT TO LICENSE AMENDMENT N0. 93 FACILITY OPERATING LICENSE NO. OPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 7-33n 3/4 7-33o B 3/4 7-6 B 3/4 7-6 B 3/4 7-7 8 3/4 7-7 B 3/4 7-8 6-22 6-22

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,a P LANT SYSTEMS 3/4.7.9 SNLBBERS LIMITING CONDITION FOR OPERATION 3.7.9 All snubbers shall be OPERAB LE.

l APP LICAB ILITY: M0CES 1, 2, 3 and 4 (M00ES 5 and 6 for snubbers located on systens required OPERABLE in those MOCES).

ACTION:

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 4.7.9c on tha supported component or declare the supported 1

system inoperable and follow appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABlf by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

a.

Visual Inspection An inservice visual inspection of all snubbers shall be performed in accordance with the following schedule for each type. As used in this specification, type of snubber shall mean snubber of the same design and manufacturer, irrespective of capacity, No. Inoperable Snubbers of Each Type per Inspection period Subsequent Inspection Period *#

0 18 months + 25%

1 12 months T 25%

2 6 months T 25%

3, 4 124 days 1 5%

7 5,6,7 62 days + 25%

8 or more 31 days f 25%

Snubbers are categorized as accessible and inaccessible during reactor operation. Each group (accessible and inaccessible) nay be inspected independently in accordance with the above schedule.

• The inspection interval shall not be lengthened more than one step at a time.

1. The provisions of Specification 4.0.2 are not applicable.

SALEM - UNIT 1 3/4 7-28 Amendment No. 93

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. PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to _the foundation or supporting structure are secure, and (3) in.those locations where snubber movenent can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up. Snubbers which appear inoperable as a result of visual inspections may be determined OPERA 8LE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the. rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.9d or 4.7.9e as applicable. However, when the fluid port of a hydraulic 1

snubber is found to be uncovered, the snubber shall be declared 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 common hydraulic fluid reservoir shall be counted as inoperable snubbers.

c.

Functional Tests At least once per 18 months during shutdown, a representative sample of 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 type of snubber that does not meet the functional test acceptance criteria of Specification 4.7.9d or 4.7.9e, an additional 10% of that type of snubber shall be functionally tested.

The representative sample selected for functional testing shall include the various configurations, operating _ environments and the range of size and capacity of snubbers. At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories:

1.

The first snubber away from each reactor vessel nozzle 2.

Snubbers within five feet of heavy equipment (valve, pump, turbine, motor,etc.)

3.

Snubbers within ten feet of the discharge from a safety relief valve j

i SA LEM - UNIT 1 3/4 7-29 Amendment No. 93 L

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

In addition to the regular sample, snubbers which failed the previous i

functional test shall be retested during the next test period.

If a i

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.

I If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested.

This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance j

criteria.

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

performed on the components which are supported by the snubber (s). The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.

d.

Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:

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1.

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

2.

Snubber bleed, or release rate, where required, is within the specified range in compression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

e.

Mechanical Snubbers Functional Test Acceptance Criteria 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. The drag force shall not have increased more than 501 since the last. functional test.

2.

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

SA LEM - UNIT 1 3/4 7-30 Amendment No. 93

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PLANT SYSTEMS-

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SURVEILLANCE REQUIREMENTS (Continued) 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.

f.

Snubber Service Life Monitorina A~ record of the. service life of each snubber, the date at which the

'l 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 6.10.2.1.

Concurrent with the first inservice visual inspection and at least once per.18 months thereafter, the installation and maintenance i

records for each snubber shall be reviewed to verify that the l- )

indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review. If the l

J 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.

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j SALEM - UNIT 1 3/4 7-31 Amendment No. 93

THIS PAGE LEFT INTENTIONALLY BLANK SA LEM - UNIT 1 3/4 7 32 Amendment No. 93

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j SAEM - UNIT 1 3/4 7-33 Amendment No. 93 4

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PLANT SYSTEMS p

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_ BASES L

l 3/4.7.9 SNUB 8ERS l

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All snubbers are required OPERABLE to ensure that the structural l

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 l nonsafety related systems and then only if their failure or failure of the l

system on which they were installed, would have no adverse effect on any safety related system.

A list of individual snubbers required to be operable per the technical specifications with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section

- i 50.71(c) of 10 CFR Part 50. The accessibility of each snubber shall be l

determined and approved by the Station Operations Review Committee. The determination shall be based on 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 I

Guide 8.8 and 8.10.

The addition or deletion of any snubber shall be made in j

accordance with Section 50.59 of 10 CFR Part 50.

t 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 determine-the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed d

(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 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 engin evaluation shall determine whether or not the snubber mode of faileering ure has imparted a significant effect or degradation on the supported component or system.

SALEM - UNIT 1 B 3/4 7-6 Amendment No. 93

PLANT SYSTEMS BASES

' SNUBBERS (Continued)

To provide assurance of snubber functional reliability, a representative l sample of the installed snubbers will be functionally tested during plant shutdowns at 18-month intervals. Observed failures of these sample snubbers l

shall require functional testing of additional units.

Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the-snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent date. Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.

Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance program.

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in 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.

3/4.7.10 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 l

located. The fire suppression system consists of the water system, spray

[

and/or sprinklers, CO2, and fire hose stations. The collective capability of l the fire suppression systems is adequate to minimize potential damage to safety-related equipment and is a major element in the facility fire l

protection program.

In the event that portions of the fire suppression systems are inoperable,l alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.

l In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I report to the Comission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.

l SALEM - UNIT 1 B 3/4 7-7 Amendment No. 93

PLANT SYSTEMS BASES 3/4.7.11 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the facility fire' protection program and are subject to periodic inspections.

During periods of time when the barriers are not functional, a continuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status.

I SALEM - UNIT 1 8 3/4 7-8 Amendment No. 93

E ADMINISTRATIVE CONTROLS 6.10.2 -The following records shall.be retained for the duration of the Unit Operating License:

a.

Records and drawing' changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

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

c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs, Records of. transient or operational cycles for those facility e.

components identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

g.

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

Records of in-service inspections performed pursuant to these Technical Specifications.

i.

Records of Quality Assurance activities required by the QA Manual.

j.

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

k.

-Records of meetings of the SORC and the NRB.

1.

Records for Environmental Qualification which are covered under the provisions of Paragraph 6.16.

m.

Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service life commences and l

associated installation and maintenance records.

n.

Records of secondary water sampling and water quality.

o.

Records of analyses required by the radiological environmental monitoring program which would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.

SALEM - UNIT 1 6-22 Amendment No. 93

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UNITED STATES g

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PUBLIC SERVICE ELECTR_IC & GAS COMPANY PHILADELPHIA ELECTRIC-COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY 00CKET NO. 50-311 SALEN GENERATING STATION, UNIT NO 2 AMENDNENT T0_F_ACILITY' OPERATING LICENSE Amendment No. 68 License No. DPR-75 1.

The Nuclear Pegulatory Comission (the Consnission or the NRC) has found that:

A.

The application for amendment filed by the Public Service Electric &

Gas Company, Philadelphia Electric Company,(Delmarva Power and Light Company and Atlantic City Electric Company thelicensees) dated April 14,1987 as supplemented by letter dated October 5,1988, 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; 1

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission;.

C.

There is reasonable assurance: (1) 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 Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon 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 Comission'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 Facility Operating License No. OPR-75 is hereby amended to read as follows:

___-_-__-____.___7___

2-(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 68., are hereby incorporated in the license. The licensee shall operate the facility in accordance with

'the Technical Specifications..

3.

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

FOR THE NUCLEAR. REGULATORY COMMISSION Mohan C. Thadani for Walter R. Butler, Director q)

Project Directorate I-2

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Division of_ Reactor Projects I/II

Attachment:

I Changes to the Technical Specifications Date of-Issuance: May 1, 1989 3

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, l (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

68, are hereby incorporated in the license.. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Walter R.

utler, Director Project Directorate I-2 Division of Reactor Proj< cts I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: May 1, 1989 i

m

_______m_.__

e ATTACHMENT TO LICENSE AMENDNENT NO, 68 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 i

Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 7-23 3/4 7-23 3/4 7-24 3/4 7-24 3/4 7-25 3/4 7-25 3/4 7-26 3/4 7-26 3/4 7-27 3/4 7-27 thru 3/4 7-30 3/4 7-28 3/4 7-29 3/4 7-30 3/4 '-30a 3/4 7-30b 3/4 7-30c 3/4 7-30d 3/4 7-30e 3/4 7-30f 3/4 7-30g 3/4 7-30h 3/4 7-301 3/4 7-30.1 3/4 7-30k 3/4 7-301 B 3/4 7-6 B 3/4 7-6 l

L a ATTACHMENT TO LICENSE AMENDMENT NO. 68 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:

Remove Pages Insert Pages B 3/4 7-7 B 3/4 7-7 B 3/4 7-8 8 3/4 7-8 6-22 6-22 i

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i PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9 All snubbers shall be OPERAB LE.

APP LICAB ILITY: MODES 1, 2, 3 and 4 (MODES 5 and 6 for snubbers located on systers required OPERA 8 LE in those M00ES).

ACTION:

With one or more snubbers inoperable, within 7? hours, replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation

peri,

ication 4.7.9c on the supported component or declare the supported systi :

operable and follow appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERA 8 LE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

a.

Visual Inspection An Inservice visual inspection of all snubbers shall be performed in accordance with the following schedule for each type. As used in this I

specification, type of snubber shall mean snubber of the same design and manufacturer, irrespective of capacity.

No. Inoperable Snubbers of Each Type per Inspection Period Subsequent Inspection Period *#

0 18 months + 25%

1 12 months T 25%

2 6 months T 25%

3, 4 124 days + 75%

5,6,7 62 days T 25%

8 or more 31 days E 25%

Snubbers are categorized as accessible and inaccessible during reactor operati on. Each group (accessible and inaccessible) ngy be inspected independently in accordance with the above schedule.

• The inspection interval shall not be lengthened more than one step at a time.

1. The provisions of Specification 4.0.2 are not applicable.

Amendment No.68 SALEM - UNIT 2 3/4 7-23 1

s, PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement I

and is not frozen up. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABE for the purpose of establishing the next visual inspection interval, providing that (1) t 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 4.7.9d or 4.7.9e as applicable. However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared 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 common hydraulic fluid reservoir shall be counted as inoperable snubbers.

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c.

Functional Tests At least once.per 18 months during shutdown, a representative sample of 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 type of snubber that does not meet the functional test acceptance criteria of Specification 4.7.9d or 4.7.9e, an additional 10% of that type of snubber shall be functionally tested.

i 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 five feet of heavy equipment (valve, pump, turbine, motor,etc.)

3 Snubbers within ten feet of the discharge from a safety relief valve SALEM - UNIT 2 3/4 7-24 Amendment No. 68 I

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.

If a l

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.

If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be f nctionally tested.

This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.

For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s). The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely af.fected by the inoperability of the snubber (s) in order to ensure that' the supported component remains capable of meeting the designed service.

d.

Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:

1.

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

2.

Snubber bleed, or release rate, where required, is within the specified range in compression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

e.

Mechanical Snubbers Functional Test Acceptance Criteria 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 i

force. The drag force shall not have increased more than 50% since the last functional test.

2.

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

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SALEM - UNIT 2 3/4 7-25 Amendment No.68 1

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3.

Snubber rolossa reto, wh ra r: quired, is within tha cpecified rrnga in co:pracsion or tenaicn. Fce snubbero cp;cificolly rIquir:d not to dicplcca und:r centinu:un lecd, the ability of the snubber to withstand load without displacement shall be verified.

f.

Snubber Service Life Monitorina i

A record of the service life of each snubber, the date at which the designated service life commences and the installation and l maintenance records on which the designated se"vice life is' based j

shall be maintained as required by Specification 6.10.2.1.

{

Concurrent with the first inservice visual inspection and at i

least once per 18 months thereafter,,the installation and maintenance records for each snubber shall be reviewed to verify l

that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.

Ifl 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.

l SALEM - UNIT 2 3/4 7-26 Amendment No.68

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s, PAGES 3/4 7-27 thru 3/4 7-301 ARE E LETE D SA LEM - UNIT 2 3/4 7-27 thru 3/4 7-30 Amendment No. 68

PLANT SYSTEMS g ',

BASES 3/4.7.9 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems I

is maintained during and following a seismic or other event initiating dynamic l

loads.

Snubbers excluded from this inspection program are those installed on nonsafety related systems and then only if their failure or failure of the l

system on which they were installed, would have no adverse effect on any safety-related system.

A list of individual snubbers required to be operable per the technical specifications 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 Station Operations Review Consnittee. The l

determination shall be based on 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 Guide 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.

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 recuired 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 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 componert 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.

SALEM - UNIT 2 B ?/4 7-6 Amendment No. 68

,e plAWT SYSTEMS

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' BASES i

SNUBBERS (Continued)

To provide assurance of snubber functional reliability, a representative f

sample of the installed snubbers will be functionally tested daring plant shutdowns at 18-month intervals. Observed failures of these sample snubbers shall require functional testing of additional units.

Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission, if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent J

date.

Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.

Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in 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.

3/4.7.10 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 l

located. The fire suppression system consists of the water system, spray and/or sprinklers, CO2, and fire hose stations. The collective capability of the 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 system are inoperable, alternate backup fire-fighting equipment is required to be made available in the affected areas until 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 fighting than if the inoperable equipment.is the i

primary means of fire suppression.

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l SALEM - UNIT 2 B 3/4 7-7 Amendment No.68

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.,.. ;. a PLANT SYSTEMS 1

8ASES 3/4.7.10 FIRE SUPPRESSION SYSTEMS (Continued)

In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken_since this system provides the major fire suppression capability of the plant. The requirement for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> report to the Comission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.

3/4.7.11' PENETRATION FIRE BARRIERS

'The OPERABILITY of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.

Fire barrier penetrations, including cable penetration barriers, fire doors and dampers are considered OPERABLE when the visually observed condition i

is the same as the as-designed condition. For those fire barrier penetrations that are not in the as-designed condition, an evaluation shall be performed to show that the modification has not degraded the fire rating of the fire barrier penetration.

Duringperiods.oftimewhenabarrierisinoperable,eikher1)a continuous fire watch is required to be maintained in the vicinity of the affected barrier, or 2) the fire detectors on at least one side of the affected barrier must be verified OPERABLE and an hourly fire watch patrol established, until the barrier is restored to OPERABLE status.

SALEM - UNIT 2 B 3/4 7-8 Amendment No. 68

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ADMINISTRATIVE CONTROLS 6.10.2 The following records shall be retained for the duration of the Unit 3

3' Operating License:-

Records and drawing changes reflecting unit design modifications a.

made to systems and equipment described in the Final Safety Analysis Report.

b.

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

Records of radiation exposure for all individuals entering radiation c.

control areas.

i d.

Records of gaseous and liquid radioactive material released to the environs.

i Records of transient or operational cycles for those facility e.

components identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

i g.

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

h.

Records of in-service inspections performed pursuant to these Technical Specifications.

1.

Records of Quality Assurance activities require by the QA Manual.

j.

Recordsifreviewsperformedforchangesmadetoproceduresor equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the SORC and the NR8.

1.

Records for Environmental Qualification which are covered under the provisions of Paragraph 2.C(7) and 2.C(8) of Facility Operating License DPR-75.

Records of the service lives of all hydraulic and mechanical m.

snubbers including the date at which the service 1tfe comences and i associated installation and maintenance records.

n.

Records of secondary water sampling and water quality.

o.

Records of analyses required by the radiological environmental monitoring program which would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.

SALEM - UNIT 2 6-22 Amendment No. 68

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