ML17139B373

Amend 11 to License NPF-14,revising Tech Specs in Response to Generic Ltrs 82-17 & 82-23

ML17139B373
Person / Time
Site:	Susquehanna
Issue date:	02/24/1983
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML17139B374	List: ML17139B373 ML17139B375 ML17139B376
References
GL-82-17, GL-82-23, NUDOCS 8303020461
Download: ML17139B373 (12)

Text

PENNSYLVANIA POWER 5'LIGHT COMPANY SUSQUEHANNA'S A

Amendment No. 11 License No. NPF'14 1.

The Nuclear Regulatory Coomission (the Commission or the NRC) having found that:

A.

The application for an amendment filed by the Pennsylvania Power 8 Light Company, dated December 10, 1982 and February 8, 1983 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; 8.

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

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering tHe health and safety of the public, and (ii) that such activities will be conducted in compliance arith the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comnission'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 the Facility Operating License No. NPF-14 is hereby amended to read as follows:

(2)

Technical"Specifications.and.Environmental-Protection-Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 11

, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license.

PP8L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

OFFICE/

SURNAME/

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This amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COWISSIOH 01'igfa8$ sfgiied by:

A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

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ATTACHMENT TO-t.ICENSE-AMENDMENT NO:-i]-

A 4

Replace the following pages of the Appendix "A" Technical Specifications with enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

REMOVE 3/4 3-29 3/4 3-30 6-11 6-12 6-17 6-18 INSERT 3/4 3-29 3/4 3-30 6-11 6-12 6-17 6-18

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D TRIP FUNCTION 4.

AUTOMATIC DEPRESSURIZATION SYSTEM MINIMUM OPERABLE APPLICABLE CHANNELS Pg TRIP OPERATIONAL SYSTEM CONDITIONS TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION b.

C.

d.

e.

g-Reactor Vessel Water Level -

Low Low Low, Level 1

Drywell Pressure - High ADS Timer Core Spray Pump Discharge Pressure - High (Permissive)

RHR LPCI Mode Pump Discharge Pressure

- High (Permissive)

Reactor Vessel Water Level - Low, Level 3 (Permissive)

Manual Initiation 2

2 1

1/loop 1/loop l

1/valve 1

2 3

1, 2, 3

1, 2, 3

1, 2, 3

1.2 3

1 2

3 1, 2, 3

30 30 31 31 31 31 33 5.

LOSS OF POWER TOTAL NO.

OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE OPERATIONAL CONDITIONS ACTION 1/bus 1/bus 2/bus 1,

2 3

4IICIN:

5IN:III 36 a.

4.16 kv ESS Bus Under-voltage (Loss of Voltage, 1/bus 3

4NCNC 5IIIIIC 35

<20K) b.

4.16 kv ESS Bus Under-voltage (Degraded Voltage, 2/bus 2/bus 1, 2, 3, 4"", 5""

36

<65K) c.

4. 16 kv ESS Bus Under-voltage (Degraded Voltage 2/bus 2/bus 2/bus

<84K)

(a)

A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.

(b)

One trip system.

Provides signal to HPCI pump suction valves only.

('c)

Two out of two. logic.

When the system is required to be OPERABLE per Specification 3.5.2.

¹ Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 150 psig.

Required when ESF equipment is required to be OPERABLE.

¹¹ Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 100 psig.

ACTION 30-ACTION 31-ACTION 32-ACTION 33-ACTION 34-ACTION 35-ACTION 36-TABLE 3.3. 3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

a.

For one trip system, place the inoperable trip system in the tripped condition within one hour*

or declare the associated ECCS inoperable.

b.

For both trip systems, declare the associated ECCS inoperable.

I With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, declare the associated ECCS inoperable.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place the inoperable channel in the tripped condition within one hour.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the associated ECCS inoperable.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within one hour" or declare the HPCI system inoperable.

With the number of OPERABLE channels less. than the Total Number of Channels, declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8. 1. 1 or 3.8. 1.2, as appropriate.

With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped condition-within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />;~ operation may-.then continue until performance of the next required CHANNEL FUNCTIONAL TEST.

e provsssons of Specification 3.0.4 are not applicable.

SUS(UEHANNA - UNIT 1 3/4 3-30

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ADMINISTRATIVE CONTROLS REVIEW (Continued) d.

Proposed changes to Appendix A Technical Specifications or this Operating License.

e.

Violations of codes, regulations,

orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.

g.

Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.

h.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures,

systems, or components that could affect nuclear safety.

Reports and meetings minutes of the PORC.

AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the SRC.

These audits shall encompass:

ao The conformance of unit operation to provisions contained within the Appendix A Technical Specifications and applicable license conditions at least once per 12 months.

rI b.

The performance, training and qualifications of the entire unit staff at least once per 12 months.

C.

The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

d.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.

e.

The Emergency Plan and implementing procedures at least once per 12 months.

The Secur ty Plan and implementing procedures at least once per:

12 months.

g.

h.

Any other aiea of unit operation considered appropriate by the SRC or the Senior Vice President-Nuclear.

The Fire Protection Program and implementing procedures at least once per 24 months.

.SUSQUEHANNA " UNIT 1 6"ll AMENDMENT NO.

ADMINISTRATIVE CONTROLS AUDITS n.

(Continued)

An independent fire protection and loss prevention inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.

An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 36 months.

The radiological environmental monitoring pro'gram and the results thereof at least once per 12 months.

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

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

The performance of activities required by the guality Assurance Program to meet the criteria of Regulatory Guide 4.15,

December, 1977, at least once per 12 months.

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

RECORDS 6.5.2.10 Records of SRC activities shel) be prepared, approved,and distributed as indicated below:

a.

b.

Minutes of each SRC meeting shall be prepared, approved and forwarded to the Senior Vice Pres(dent-Nuclear within 14 days following each meeting.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be

'prepared, approved and forwarded to the Senior Vice President-Nuclear within 14 days following completion of the review.

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

SUS(UEHANNA - UNIT 1 6-12

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ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORTS 6.9. 1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the main steam system safety/

relief valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U. S. Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy to the Regional Administrator of the Regional Office no later than the 15th of each month following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change(s) was made effective.

In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the PORC.

REPORTABLE OCCURRENCES

6. 9. 1.7 The REPORTABLE OCCURRENCES of Specifications

6. 9. 1.8 and 6. 9. 1,.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC.

Supplemental reports may be required to fully describe final resolution of occurrence.

In case of corrected or supplemental

reports, a licensee event report shall be completed and reference shall be made to the original report date.

PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.8 The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Regional Administrator of the Regional Office, or his designate no later than the first working day following the event, with a written followup report

-"-'ithin 14 days.

The written followup report shall include, as a minimum, a

completed copy of a licensee event report form.

Information provided on the licensee event report form shall be supplemented, as

needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a ~

Failure of.the reactor protection system or other systems subject to limiting safety system settings'o initiate the required protective function by the time a monitored parameter reaches the setpoint speci-fied as the limiting safety system setting in the technical specifica-tions or failure to complete the required protective function.

b.

Operation of the unit or affected systems when any parameter or:

operation subject to a limiting condition for operation is less conservative than the least conservative aspect'of the limiting condition for operation established in the technical specifications.

c.

Abnormal degradation discovered in fuel cladding, reactor coolant pressure

boundary, or primary containment.

SUSQUEHANNA ":UNIT 1 6-17 AMENDMENT NO. 11

ADMINISTRATIVE CONTROLS PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP (Continued) d.

e.

g.

h.

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Reactivity anomalies involving disagreement with the prddicted value of reactivity balance under steady state conditions during power operation greater than or equal to 1X delta k/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified -in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5X delta k/k; or occurrence of any unplanned cr iiticality.

Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional require-ments of system(s) used to cope with accidents analyzed in the SAR.

Personnel error or procedural inadequacy which prevents or could

prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the SAR.

Conditions arising from natural or man-made events that, as a direct result of the event, require unit shutdown, operation of safety systems,'r other protective measures required by technical specifications.

Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.

I Performance of structures,

systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in

'he safety analysis report or technical specifications bases; or discovery during unit life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

Failure of main-steam line code safety/relief..valve to reseat after actuation.

k.

Offsite releases of radioactive materials in liquid and gaseous

. effluents which exceed the limits of Specification 3.11. 1. 1 or

3. 11. 2. 1.

Exceeding the limits in Specification 3.11.1.4 or'.11.2.6 for the storage of radioactive materials in the listed tanks.

The written follow-up report shall include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.

SUSQUEHANNA " UNIT 1 6-18