ML20111B000

Amends 55 & 46 to Licenses NPF-2 & NPF-8,respectively, Removing List of Snubbers from OL

ML20111B000
Person / Time
Site:	Farley
Issue date:	12/19/1984
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20111B001	List: ML20111B000
References
TAC-55409, TAC-55410, NUDOCS 8501080354
Download: ML20111B000 (34)

Text

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'o UNITED STATES 8

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NUCLEAR REGULATORY COMMISSION o

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-E WASHINGTON, D. C. 20555 ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. NPF-2 1.

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

A.

The application for amendment by Alabama Power Company (the licensee) dated July 6, 1984, complies with 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; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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; D.

The issuance of this license 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 reouirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-2 is hereby amended to read as follows:

8501080354 841219 PDR ALOCK 05000348 P

PDR

. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 55, 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 ADl{

h Sfeven A Varga, t Y

Operating Reacto anch #1 Division of Licens g

Attachment:

Changes to the Technical Specifications Date of Issuance: December 19, 1984 O

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1 ATTACHMENT TO LICENSE AMENDMENT NO. 55 AMENDMENT NO. 55 FACILITY OPERATING LICENSE N0. NPF-2 DOCKET NO. 50-348 Revised Appendix A as follows:

Remove Pages Insert Pages 3/4 4-13 3/4 4-13 3/4 4-15 3/4 4-15 3/4 6-22 3/4 6-22 3/4 7-12 3/4 7-12 3/4 7-20 3/4 7-20 3/4 7-21 3/4 7-21 3/4 7-22 3/4 7-22 3/4 7-23 3/4 7-23 3/4 7-24 3/4 7 3/4 7-25 3/4 7-25 3/4 7-26 through 7-79a B 3/4-7-5 B 3/4 7-5 6-12 6-12 6-23 6-23 f

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 9.

Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing.

This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.

b.

The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.

4.4.6.5 Reports a.

Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days.

b.

The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.

This Special Report shall include:

1.

Number and extent of tubes inspected.

2.

Location and percent of wall-thickness penetration for each indication of an imperfection.

3.

Identification of tubes plugged.

c.

Results of steam generator tube inspections which fall into Category C-3 shall be considered a REPORTABLE EVENT and shall be reported pursuant to 10CFR50.73 prior to resumption of plant operation.

The written report shall provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.

l FARLEY - UNIT 1 3/4 4-13 AMENDMENT NO. 55

TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION 5

o E

IST SMFLE INSPECTION 2ND SMFLE INSPECTION 3RD SAMLE INSPECTION f

Si Sample Size Resul t Action Required Resul t Action Required Resul t Action Required 4

A minimum of C-1 None N/A N/A N/A N/A S Tubes per i

S.G.

C-2 Plug defective C-1 None N/A N/A tubes and inspect additional 25 C-2 Plug defective C-1 None tubes in this S.G.

tubes and inspect additional 45 tubes C-2 Plug defective in this S.G.

tubes o,

C-3 Perform action for

];

C-3 result of first sample

[sn' C-3 Perform action for N/A N/A C-3 result of first sample C-3 Inspect all tubes All other None N/A N/A in this S.G.,

S.G.s are plug defective C-1 tubes and inspect 25 tubes in each Some S.G.s Perform action for N/A N/A other S.G.

C-2 but no C-2 result of additional second sample 3

S.G.s are i

Ri C-3 di i

di Notification to Additional Inspect all tubes N/A N/A i

sj NRC pursuant to S.G. i s C-3 in each S.G. and l

10CFR50.73 plug defective ca tubes.

Notification to

["

NRC pursuant to 10CFR50.73 l

S - 3 N % Where N is the number of steam generators in the unit, and n is the number of steam generators inspected N

during an inspection f

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CONTAINMENT SYSTEMS HYDROGEN MIXING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.4.4 Two independent hydrogen mixing systems shall be OPERABLE.

l APPLICABILITY:

MODES 1 and 2.

ACTION:

With one hydrogen mixing system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.4.4 Each hydrogen mixing system shall be demonstrated OPERABLE:

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At least once per 92 days on a STAGGERED TEST BASIS by starting a.

each system from the control room and verifying that the system operates for at least 15 minutes.

. r.

b.

At least once per 18 months by verifying a fan speed of at

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least 1320 rpm.

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FARLEY - UNIT 1 3/4 6-22 AMEN 0 MENT NO. 55

PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION

.3 3.7.4 At least two independent service water loops shall be OPERABLE with at least two service water pumps per loop.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With only one service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY witnin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.4 ' At least two service water loops shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each accessible a.

valve (manual, power operated or automatic) in the flow path, servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 18 months during shutdown by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a safety injection test signal.

At least once per 18 months by verifying that the buried piping c.

is leak tight by a visual inspection of the ground area.

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l FARLEY - UNIT 1 3/4 7-12 AMENOMENT NO. 55 1

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

The only snubbers excluded from this I

requirement are those installed on nonsafety-related systems and then only if their failure or the failure of the system on which they are installed would have no adverse effect on any safety-related system.

APPLICABILITY:

MODES 1, 2, 3 and 4.

(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).

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 4.7.9.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE RE'QUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of S

r.*pecification 4.0.5.

a.

Visual Inspections The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of POWER OPERATION and shall include all snubbers within the scope of Specification 3.7.9.

If less l

than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months i 25% from the date of the first inspection.

Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:

No. Inoperable Sn.ubbers Subsequent Visual per Inspection Period Ins)ection Period *#

O 13 months 125%

1 12 months i 25%

2 6 months 125%

3,4 124 days i 25%

5,6,7 62 days i 25%

8 or more 31 days i 25%

The snubbers may be categorized into two groups:

Those accessible and r

l those inaccessible during reactor operation.

Each group may 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.

FARLEY - UNIT 1 3/4 7-20 AMENDMENT NO. 55

l-PLANT SYSTEMS-1

],

SURVEILLANCE REQUIREMENTS (Continued)

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b.

Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY and (2) attachments to the foundation or supporting structure are secure.

Snubbers which appear inoperable as a result of visual inspections may be determined i

OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly i

established and remedied for that particular snubber.and for other i

snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and i

determined OPERABLE per Specifications 4.7.9.d or 4.7.9.e. as

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appl i cabl e.

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 unless the test is started with the piston in the as found setting, extending the piston rod in the tension and compression mode directions.

All snubbers connected to an inoperable common hydraulic fluid reservoir shall be cour.ted as inoperable snubbers.

c.

Functional Tests At least once per 18 months during shutdown, a representative sample of 88 snubbers shall be functionally tested either in place or in a i

bench test.

If more than 3 snubbers do not meet the functional test acceptance criteria of Specification 4.7.9.d or 4.7.9.e, an additional sample selected according to the expression 22(a-3) shall be functicnally tested, where a is the total number of snubbers found inoperable during the functional testing of the initial representative sample.

Functional testing shall continue according to the expression (22)b where b is the number of snubbers found inoperable in the previous 4

re-sample, until no additional inoperable snubbers are found within"a sample or until all. snubbers have been functionally tested.

Snubbers greater than 50,000 lb. capacity may not be excluded from functional testing requirements.*

The representative sample selected for functional testing shall l

include the various configurations, operating environments and the range of size and capacity of snubbers.

At least 25% of the snubbers i

in the initial representative sample shall include snuhbers from the l

following three categories:

1.

The first snubber away from each reactor vessel nozzle

• This portion of the specification is not effective until the fifth refueling l

outage or when a commercial in-place testing device is available whichever is later.

FARLEY - UNIT 1 3/4 7-21 AMENDMENT NO. 55 '

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 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.

Snubbers that are especially difficult to remove or in high radiation zones during shutdown shall also be included in the representative sampl e.*

Hydraulic and mechanical snubbers may be used jointly or separately as the basis for the sampling plan.

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

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

.. e 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 sn'ubber(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 attached 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.

Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable 4

basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.

FARLEY - UNIT 1 3/4 7-22 AMENDMEl!T NO.' 55

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 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 l

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 in both tension and compression.

3.

Snubber release rat'e, 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.

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I FARLEY - UNIT 1 3/4 7-23 AMENDMENT NO. 55

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

E

f. Snubber Service Life Monitoring A 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.n.

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

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FARLEY - UNIT 1 3/4 7-24 AMENDMENT NO.55

This page intentionally left blank.

3/4.7-26 through 3/4.7-79a Deleted l

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FARLEY - UNIT 1 3/4 7-25 AMENDMENT NO.55 l-

PLANT SYSTEMS BASES

- 3/4.7.9 SNUBBERS All snubbers are required OPERABLE to ensure that the structural i

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 l

if their failure or failure of the system on which they are installed, would have no adverse effect on any safety related system.

A manual, which contains a taoulation of the hydraulic and mechanical snubbers which are within the scope of Technical Specification 3/4.7.9, is j

maintained as a comprehensive list of snubbers which are to be included in the snubber inspection and test program.

The.ranual includes, as a base line, the snubbers identified in Technical Specification Tables i

3.7-4a and 3.7-4b as of License Amendment No. 43.

The manual will be controlled in accordance with 10CFR50.59.

The visual inspection frequency is based upon maintaining a j

constant level of snubber protection to systems.

Therefore, the i

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 i

elapsed may be used as a new reference point to determine the next i

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 j

and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, i

that snubber may be exempted from being counted as inoperable.

l 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.

The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or j

degradation on the attached component.

I To provide assurance of snubber functional 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(1+c/2) provides a confidence level of approximately 951 that 901 to 100% of the snubbers in the plant will be OPERABLE within acceptance limits, where c:is the l

allowable number of snubbers not meeting the acceptance criteria.

L, Observed f ailures of these sample snubbers shall require functional l'

testing of additional units.

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

FARLEY - UNIT 1 83/47-5 AMEN 0 MENT NO. 55

t ADMINISTRATIVE CONTROLS 1.

The 0FFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

m.

The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes at least once per 24 months.

At each scheduled NORB meeting, the Manager-Safety Audit and n.

l Engineering Review shall make a summary report of the above audits.

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AUTHORITY 6.5.2.9 The NORB shall report to and advise the Senior Vice President on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of NORB activities shall be prepared, approved and distributed 3

as indicated below:

=

l Minutes of each NORB meeting shall be prepared, approved and forwarded a.

to the Senior Vice President within 14 days following each meeting.

b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Senior Vice President within 4

j 14 days following completion of the review.

i c.

Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President and to the management positions responsible for the areas audited within 30 days after completion of the audit.

'6.5.3 TECHNICAL REVIEW AND CONTROL i

ACTIVITIES 1

6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

(

a.

Procedures required by Technical Specification 6.8 and other pro-l cedures which affect plant nuclear safety, and changes (other than editorial or typographical changes) thereto, shall be prepared, re-viewed and approved.

Each such procedure or procedure change shall be reviewed by an individual / group other than the individual / group which prepared the procedure or procedure change, but who may be from the same organization as the individual / group which prepared the procedure or procedure change.

Procedures other than Administrative Procedures will be approved by either the Technical Superintendent, the Oper-ations Superintendent, the Maintenance Superintendent, the Performance and Planning Superintendent, the Administrative Superintendent (Docu-ment Control and Storeroom), or an Assistant Plant Manager as l

applicable.

The Plant Manager will approve administrative procedures, security implementing procedures, emergency plan im procedures and contingency implementing procedures.plementing Temporary changes to procedures which c' early do not change the intent of the approved procedures will be approved by two members of the plant staff, at least one of whom holds a FARLEY - UNIT 1 6-12 AMENDMENT NO. 55

ADMINISTRATIVE CONTROLS h.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Unit Operating License Records and drawing changes reflecting unit design modifications made a.

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.

d.

Records of gaseous and liqui'd radioactive material released to the environs.

Records of transient or operational cycles for those unit components e.

identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

g.

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

h.

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

1.

Records of Quality Assurance activities required by the QA Manual.

j.

Records of reviews performed for changes made to procedures or l

equipment or reviews of tests and experiments pursuant to 10CFR50.59.

l k.

Records of meetings of the PORC and the NORB.

1.

Records of secondary water sampling and water quality.

m.

Records of analyses required by the radiological environmental j

monitoring program.

n.

Records of the service lives of all hydraulic and mechanical snubbers in service after 07/01/81 within the scope of 3/4.7.9 including the l

l date at which the service life commences and associated installation l

and maintenance records.

l 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

1 FARLEY - UNIT 1 6-23 AMENDMENT NO. 55 i

/

'o UNITED STATES g

8 NUCLEAR REGULATORY COMMISSION o

C E

WASHINGTON, D. C. 20555

%.....)

ALABAMA POWER COMPANY DOCKET N0. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.46 License No. NPF-8 1.

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

A.

The application for amendment by Alabama Power Company (the licensee) dated July 6, 1984, complies with 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; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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; D.

The issuance of this license 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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-8 is hereby amended to read as follows:

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2-(2)

Technical Specifications s,.

The. Technical. Specifications contained in Appendices A and B, as revised through Amendment No,46, 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 f

.even A.

a rIja, C Operating Reactors anch #1 Division of Licens

Attachment:

A Changes to the Technical Specifications Date of Issuance:

December 19, 1984 O

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ATTACHMENT TO LICENSE AMENDMENT NO.46 AMENDMENT NO.46 FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Revised Appendix A as follows:

Remove Pages Insert Pages 3/4 4-13 3/4 4-13 3/4 4-15 3/4 4-15 3/4 6-22 3/4 6-22 3/4 7-12 3/4 7-12 3/4 7-20 3/4 7-20 3/4 7-21 3/4 7-21 3/4 7-22 3/4 7-22 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 through 3/4 7-49bb 3/4 7-61 3/4 7-61 3/4 7-66 3/4 7-66 8 3/4 7-5 B 3/4 7-5 6-12 6-12 6-23 6-23 9

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 9.

Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing.

This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice i n spec ti on s.

b.

The steam generator shall oe determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.

4.4.6.5 Reports a.

Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days.

b.

The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.

This Special Report shall include:

1.

Number and extent of tubes inspected.

2.

Location and percent of wall-thickness penetration for each indication of an imperfection.

3.

Identification of tubes plugged.

c.

Results of steam generator tube inspections which fall into Category C-3 shall be considered a REPORTABLE EVENT and shall

~

be reported pursuant to 10CFR50.73 prior to resumption of plant l

operation.

The written report shall provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.

FARLEY - UNIT 2 3/4 4-13 AMENDMENT NO. 46 t

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TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION 5

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IST SAMLE INSPECTION 2W SAMLE INSPECTION 3RD SAMLE INSPECTION 7

ji Sample Size Resul t Action Required Result Action Required Result Action Required M

A minimum of C-1 None N/A N/A N/A N/A S Tubes per S.G.

C-2 Plug defective C-1 None N/A N/A tubes and inspect additional 25 C-2 Plug defective C-1 None tubes in this S.G.

tubes and inspect additional 45 tubes C-2 Plug defective in this S.G.

tubes C-3 Perform action for C-3 result of first sample 3d C-3 Perform action for N/A N/A C-3 result of first sample 5

C-3 Inspec't all tubes All other None N/A N/A in this S.G.,

S.G.s are plug defective C-1 tubes and inspect 25 tubes in each Some S.G.s Perform action for N/A N/A other S.G.

C-2 but no C-2 result of additional second sample 2

S.G.s are Si C-3 di si Notification to Additional Inspect all tubes N/A N/A 35 NRC pursuant to S.G. is C-3 in each S.G. and 10CFR50.'/3 plug defective c) tubes.

s 4,

Notification to ch NRC pursuant to 10CFR50.73 S - 3 N % Where N is the number of steam generators in the unit, and n is the number of ste3:n generators inspected Tr during an inspection

CONTAINMENT SYSTEMS HYDROGEN MIXING SYSTEM

- LIMITING CONDITION FOR OPERATION 3.6.4.4 Two independent hydrogen mixing systems shall be OPERABLE.

l APPLICABILITY:

MODES 1 and 2.

ACTION:

With one hydrogen mixing system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.4.4 Each hydrogen mixing system shall be demonstrated OPERABLE:

l At least once per 92 days on a STAGGERED TEST BASIS by starting a.

each system from the control room and verifying that the system operates for at least 15 minutes.

b.

At least once per 18 months by verifying a fan speed of at least 1320 rpm.

I

(

FARLEY - UNIT 2 3/4 6-22 AMENDMENT NO.46

PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4 At least two independent service water loops shall be OPERABLE with at least two service water pumps per loop.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With only one service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.4 ' At least two service water loops shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each accessible a.

valve (manual, power operated or automatic) in the flow path, servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 18 months during shutdown by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a safety injection test signal.

At least once per 18 months by verifying that the buried piping c.

is leak tight by a visual inspection of the ground area.

O f

FARLEY - UNIT 2 3/4 7-12 AMENDMENT NO.46

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

The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their failure or the failure of the system on which they are installed would have no adverse effect on any safety-related system.

APPLICABILITY:

MODES 1, 2, 3 and 4.

(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).

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 4.7.9.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS 4.7.9 Each sr.ubber shall be demonstrated OPERABLE by performance of the

, following augmented inservice inspection program and the requirements of

, Specification 4.0.5.

a.

Visual Inspections The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of POWER OPERATION and shall include all snubbers within the scope of Specification 3.7.9.

If less l

than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months t 25% from the date of the first inspection.

Otherwise, subsequent visual inspections shall be performad in i

accordance with the following schedule:

No. Inoperable Snubbers Subsequent Visual per Inspection Period Ins)ection Period *#

l 0

13 months t 25%

l 1

12 months t 25%

l 2

6 months 125%

3,4 124 days t 25%

5,6,7 62 days i 25%

8 or more 31 days t 25%

The snubbers may be categorized into two groups:

Those accessible and those inaccessible during reactor operation.

Each group may be inspected independently in accordance with the above schedule.

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

1. The provisions of Specification 4.0.2 are not applicable.

FARLEY - UNIT 2 3/4 7-20 AMESDMENT NO.46 i

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

Visual Inspection Acceptsnce Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY and (2) attachments to the foundation or supporting structure are secure.

Snubbers which appear inoperable as a result of visual inspections may be determined i

OPERABLE 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 affacted snubber is functionally tested in the as found condition and determined OPERABLE per Specifications 4.7.9.d or 4.7.9.e. 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 unless the test is started with the piston in the as found setting, extending the piston rod in the tension and compression mode directions.

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 88 snubbers shall be. functionally tested either in place or in a bench test.

If more than 3 snubbers do not meet the functional test acceptance criteria of Specification 4.7.9.d or 4.7.9.e. an additional sample selected according to the expression 22(a-3) shall be functionally tested, where a is the total number of snubbers found inoperable during the functional testing of the initial representative i

sample.

Functional testing shall continue according to the expression (22)b 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.

l Snubbers greater than 50,000 lb. capacity may not be excluded from functional testing requirements.*

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 initial representative sample shall include snubbers from the following three categories:

1.

The first snubber away from each reactor vessel nozzle.

i This portion of the specification is not effective until the second refueling outage or when a commercial ir.-place testing device is available whichever is l ate r.

FARLEY UNIT 2 3/4 7-21 AMENDMENT NO.46 l

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.

Snubbers within five feet of heavy eau '<.nent (valve, pump, d

turbine, motor, etc.)

3.

Snubbers within 10 feet of the discharge from a safety relief valve.

Snubbers that are especially difficult to remove or in high radiation zones during shutdown shall also be included in the representative s ampl e.*

Hydraulic and mechanical snubbers may be used jointly or separately as the basis for the sampling plan.

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.

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

+

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 affected by the inoperability of the snubber (s) in order to ensure that the attached componer.t 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.

• Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.

FARLEY - UNIT 2 3/4 7-22 AMENDMENT NO. 46

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4 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 l

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 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.

t.

• f a

e FARLEY - UNIT 2 3/4 7-23 AMENDMENT NO.46

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

f. Snubber Service Life Monitoring A 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.n.

Concurrent with the first inservice visual inspection a'nd at least once per 18 months thereafter, the installation and maintenance records for each snubber shall be reviewed to verify.that the I'

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 t'he 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 rec 6rds.

O l

FARLEY - UNIT 2 3/4 7-24 AMENDMENT NO.46

d This page intentionally left blank.

3/4.7-26 through 3/4.7-49 bb Deleted S

I r

FARLEY - UNIT 2 3/4 7-25 AMENDMENT NO. 46

I TABLE 3.7-6 LIST OF FIRE HOSE STATIONS AUXILIARY BUILDING LOCATION (Room No.)

ELEVATION HOSE CABINET NO.

2103 83'-0" N2V43-D-103 2110 83'-0" N2V43-0-102 2161 100'-0" N2V43-D-110 2163 100'-0" N2V43-D-109 2164 100'-0" N2V43-0-124 2185 100'-0" N2V43-D-108 2186 100'-0" N2V43-D-131 2189 100'-0" N2V43-0-107 2208 121'-0" N2V43-0-128 2209 121'-0" N2V43-D-104 2210 121'-0" N2V43-D-126 2223 121'-0" N2V43-0-127 2234-121'-0" N2V43-D-125 2237 121'-0" N2V43-D-132 2312 139'-0" N2V43-0-114 2316 139'-0" N2V43-0-111 2319 139'-0" N2V43-D-116 2319 139'-0" N2V43-D-119 2332 139'-0" N2V43-D-113 2334 139'-0" N2V43-D-117 2345 139'-0" N2V43-D-112 2409 155'-0" N2V43-D-122 l

2408 155'-0" N3V43-D-123 2446 155'-0" N2V43-D-105 2452 155'-0" N2V43-D-120 2453 155'-0" N2V43-D-121 l

2462 155'-0" N2V43-D-106

?502 175'-0" N2V43-D-101 2505 184'-0" N2V43-D-100 2602 130'-0" N2V43-D-118 l

AUXILIARY BUILDING TO DIESEL GENERATOR BUILDING TUNNELS i

TRAIN A TUNNEL TRAIN 8 TUNNEL NOSE CABINET NO.

HOSE CABINET NO.

N2Y430001A N2Y430001P N2Y430001B N2Y43D001Q l

N2Y430001C N2Y430001R N2Y430001D N2Y4300015 N2Y430001E N2Y430001T N2Y430001F N2Y430001U t

N2Y430001G N2Y430001V N2Y430001H N2Y430001W i

N2Y430001J N2Y430001X N2Y430001K N2Y430001Y N2Y430001L N2Y430001Z N2Y430001M N2Y430002A l

N2Y430001N N2Y430002B FARLEY-UNIT 2 3/4 7-61 Amendment No. 46

Table 3.7-8 AREA TEMPERATURE MONITORING AREA TEMPERATURE LIMIT (*F) 1.

ESF Pumg_ Room:

a.

RHR Pump 2A 150*F b.

RHR Pump 2B 150*F c.

AFW Pump 2A 150*F d.

AFW Pump 2B 150*F e.

CCW Pump Room 150*F f.

Containment Spray Pump 2A 150*F g.

Containment Spray Pump 2B 150*F h.

' Charging Pump Room 2'A 150*F i.

Charging Pump Room 2B 150*F j.

Charging Pump Room 2C 150*F 2.

Electrical Areas:

a.

MCC 2A Room 150*F b.

MCC 2B Room 150*F-c.

600 Volt Load Center 2D Room 150*F d.

600 Volt Load Center 2E Room 150*F e.

Battery Charger Room A 120*F f.

Battery Charger Room B 120*F l

g.

Battery Room A 120*F h.

Battery Room B 120*F i.

Diesel Generator Rooms 150*F j.

Diesel Generator Switchgear Rooms 150*F FARLEY - UNIT 2 3/4 7-66 AMENDMENT NO.46 i

PLANT SYSTEMS BASES

-3/4.7.9 SNUBBERS i

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. A manual, which contains a tabulation of the hydraulic and mechanical snubbers which are within the scope of Technical Specification 3/4.7.9, is maintained as a comprehensive list of snubbers which are to be included in the snubber inspection and test program.

The manual includes, as a baseline, the snubbers identified in Technical Specification Tables 3.7-4a and 3.7-4b as of License Amendment No. 34 and also includes the changes identified in Alabama Power Company letter dated December 8, 1983 entitled " Safety-Related Snubber Technical Specification Table Changes".

The manual will be controlled in accordance with 10CFR50.59.

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 l

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 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.

l When a snubber is found inoperable, an engineering evaluation is L

performed.

The engineering evaluation shall determine whether or not i

the snubber mode of failure has imparted a significant effect or degradation on the attached component.

To provide assurance of snubber functional reliability, a 6

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(1+C/2) provides a confidence level of approximately 95% that 90% to 100% of the snubbers in the plant will be OPERABLE within acceptance limits, where c is the allowable number of snubbers not meeting the acceptance criteria.

Observed failures of these sample snubbers shall require functional testing of additional units.

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

FARLEY - UNIT 2 B3/4 7-5 AMENDMENT NO.

ADMINISTRATIVE CONTROLS 3

1.

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months, The PROCESS CONTROL PROGRAM and implementing procedures for m.

solidification of radioactive wastes at least once per 24 months, At each scheduled NORB meeting, the Manager-Safety Audit and n.

Engineering Review shall make a summary report of the above audits.

-AUTHORITY 6.5.2.9 The NORB shall report to and advise the Senior Vice President on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

1 RECORDS 6.5.2.10 Records of NORB activities'shall be prepared, approved and distributed as indicated below:

Minutes of each NORB mee' ting shall be prepared, approved and forwarded.

a.

to the Senior Vice President within 14 days following each meeting.

i b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Senior Vice President within 14 days following completion of the review.

Audit reports encompass ~ed by Section 6.5.2.8 above, shall be forwarded c.

to the Senior Vice President and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

Procedures required by Technical Specification 6.8 and other pro-a.

cedures which affect plant nuclear safety, and changes (other than i

editorial or typographical changes) thereto, shall be prepared, re-viewed and approved.

Each such procedure or procedure change shall be reviewed by an individual / group other than the individual / group which prepared the procedure or procedure change, but who may be from the same organization as the individual / group which prepared the procedure or procedure change.

Procedures other than Administrative Procedures will be approved by either the Technical Superintendent, the Oper-ations Superintendent, the Maintenance Superintendent, the Performance and Planning Superintendent, the Administrative Superintendent (Document Control and Storeroom), or an Assistant Plant Manager as applicable.

The Plant Manager will approve administrative procedures, security implementing procedures, emergency plan implementing procedures and contingency implementing procedures.

Temporary changes to procedures which clearly do not change the intent of the approved procedures will be approved by two members of the plant staff, at least one of whom holds a FARLEY - UNIT 2 6-12 AMENDMENT NO.46

ADMINISTRATIVE CONTROLS h.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Unit Operating License:

Records and drawing changes reflecting unit design modifications made a.

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.

d.

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

1 Records of transient or operational cycles for those unit components e.

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 facility staff.

h.

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

1.

Records of Quality Assurance activities required by the QA Manual.

1

~

l j.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10CFR50.59.

k.

Records of meetings of the PORC and the NORB.

1.

Records of secondark water sampling and water quality.

Records of analyses required by the radiological environmental m.

monitoring program.

n.

Records of the service lives of all hydraulic and mechanical snubbers within the scope of 3/4.7.9 including the date at which the service life commences and associated installation and maintenance records.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

FARLEY - UNIT 2 6-23 AMENDMENT NO. 46 l

l l

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