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Proposed Tech Spec Changes Re Administrative Controls, Special Test Exemption for Oxygen Concentration,Leakage in RCS & Refueling Operations
	ML17139B235
Person / Time
Site:	Susquehanna
Issue date:	12/10/1982
From:	; PENNSYLVANIA POWER & LIGHT CO.
To:	;
Shared Package
ML17139B234	List: ML17139B235; PLA-1430, Application for Amend 15 to License NPF-14,consisting of Proposed Changes to Tech Specs Re Administrative Controls, Special Test Exemption for Oxygen Concentration,Leakage in RCS & Refueling Operations;
References
	NUDOCS 8212170272
	Download: ML17139B235 (18)
	v • d • e

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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

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nuclear safety significance.

f.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

i.

Reports and meetings minutes of the PORC.

AUDITS 6.5.2e8 Audits of unit activities shall be performed under the cognizance of the SRC.

These audits shall encompass:

a.

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

b.

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

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 guality Assurance Program to meet the criteria of Appendix "B", 10 CFft 50, at least once per 24 months.

e.

The Emergency Plan and implementing procedures at least once per g4 months.

l2 The Security Plan and implementing procedures at least once per 24 months.

g.

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

h.

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

82i2i70272 82i2i0 PDR ADOCK 05000387 P

PDR SUSQUEHANNA " UNIT1, 6-11

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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.

h.

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

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

systems, or components that could affect nuclear safety.

i.

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:

a 0 The conformance of unit operation to provisions contained within the Appendix A Technical Specifications and applicable license conditions at least once per 12 months.

b.

C.

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

e 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 guality 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 24 months.

g.

The Security Plan and implementing procedures at least once per

~ months.

l2 Any other area of unit operation considered appropriate by the SRC or the Senior Vice President-Nuclear.

h.

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

SUSQUEHANNA " UNIT 1 6-11

ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORTS ganag<mo4 Xw@rnek~~ 8r~ch, ><ice. o( R~u.rcc. R~<yw~

6.9. 1.6 Routine reports of operating statistics and shutdown experience, incl.uding documentation'f all challenges to the main steam system safety/

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U. S. Nuclear Regulatory Commission, Mashington, 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 CALCUliATION MANUAL shall be submitted with the Monthly Operating Report within 90 da)s 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

-8 6.9. 1.7 The REPORTABLE OCCURRENCES of Specifications 6.9. 1.8 and 6'. 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 MRITTEN FOLLONUP 6.9.1<8 The types of events. listed below shall be reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by

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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 within 14 days

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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.

aO Failure of the reactor protection system 'or other systems subject to limiting safety system settings to 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.

e b.

C.

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.

II Abnormal degradation discovered in fuel cladding, reactor coolant pressure

boundary, or primary containment.

SUSQUEHANNA - UNIT 1 6-17

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r SPECIAL TEST EXCEPTIONS 3/4. 10. 5 OXYGEN CONCENTRATION

.LIMITING CONDITION FOR OPERATION 3.10.5 The provisions of Specification 3.6.6.4 may be suspended during the performance of the Startup Test Program until either the required 100K of RATED THERMAL POMER trip tests have been completed or the reactor has operated for 120 Effective Full Power Days.+

APPLICABILITY:

OPERATIONAL CONDITION 1.

ACTION Nth the requirements of the above specification not satisfied, be in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE UIREMENTS 4.10.5 The Effective Full Power Days of operation shall be verified to be less than 120, by calculation, at least once per 7 days during the Startup Test Program.

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, REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3. 2 aO b.

Ci Reactor coolant system leakage shall be limited to:

No PRESSURE BOUNDARY LEAKAGE.

5 gpm UNIDENTIFIED LEAKAGE.

25 gpm total leakage averaged over any 24-hour period.

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d.

1 gpm leakage at a reactor coolant system pressure of 1000 a 10 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1.

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APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

aO b.

Ci With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With any reactor coolant system leakage greater than the limits in b and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next'2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two closed manual or deactivated automatic valves, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With one or more of the high/low pressure interface valve leakage pressure monitors shown in Table 3.4.3.2-1 inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm pressure at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; restore the inoperable monitor(s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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g~iace nod~ 5 8 REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS 4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

a.

Monitoring the primary containment atmospheric particulate and gaseous radioactivity at least once per ~hours, and

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b.

Monitoring the drywell floor drain sump 'level at least once per

~ hours.

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4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:

a.

At least once per 18 months, and b.

Prior to returning the valve to service following maintenance, repair

. or-replacement work on the valve which could affect its leakage rate.

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.

4.4.3.2.3 The high/low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with the alarm setpoints per Table 3.4.3.2-1 by performance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and b.

CHANNEL CALIBRATION at least once per 18 months.

SUSQUEHANNA - UNIT 1 3/4 4-8

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p 17lt~P&lT 3/4. 9 REFUELING OPERATIONS 3/4.9. 1 REACTOR NODE SMITCH 0

LIMITING CONDITION FOR OPERATION 3.9. 1 The reactor mode switch shall be OPERABLE and locked in the Shutdown or Refuel position.

Mhen the reactor mode switch is locked in the Refuel position:

a.

A control rod shall not be withdrawn u'nless the Refuel position one-rod-out interlock is OPERABLE.

b.

CORE ALTERATIONS shall not be performed using equipment associated with a Refuel position interlock unless at least the following associ-ated Refuel position interlocks are OPERABLE for such equipment.

1.

2.

3.

5.

All rods in.

Refuel platform position.

Refuel platform hoists fuel-loaded.

Fuel grapple position.

Service platform hoist fuel-loaded..

APPLICABILITY:

OPERATIONAL CONDITION 5* kp,~~

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. ACTION:

a.

Nth the reactor mode switch not locked in the Shutdown or Refuel position as specified, suspend CORE ALTERATIONS and lock the reactor mode switch in the Shutdown or Refuel position.

b.

Mith the one-rod-,out interlock inoperable, lock the-reactor mode switch in the Shutdown position.

c.

Mith any of the above required Refuel position equipment interlocks isoperable, suspend CORE ALTERATIONS with equipment associated "with the inoperable Refuel position equipment interlock.

See Spec)al Test xceptions

3. 10. 1 and 3. 10.3.

8 The reactor shall be maintained in OPERATIONAL CONDITION 5 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

kfThe reactor mode switch may be placed in the Run or Startup/Hot Standby position to test the switch interlock functions provided that all control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.

SUS(UEHANNA - UNIT 1 3/4 9"1

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ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS Continued

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2.

ecting and functionally testing a representative sam of each p

of fuse on a rotating basis.

Each repre ative sample of fuse all include at least lOX of al ses of that type.

The functiona st shall consist of on-destructive resistance measurement te hich demo ates that the fuse meets its manufacturer's desig sa.

Fuses found inoperab during these functional test~i s

a ~e replaced with OPERABLE fuses prior to resuming~p~ation.

For ha~ fuse found inopera during'these funct'ests, an additionalWe resentative sam of at least 10 all fuses of that type shall b

unctionally tested u

no more failures are found or all fuses o

at ty ve been functionally tested.

b.

At least once per 60 months by subjecting each circuit breaker.to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer s recommendations.

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CONTAINMENT SYSTEMS DRYWELL AVERAGE AIR TEMPERATURE

.9 LIMITING CONDITION FOR OPERATION 3.6. 1.7 Drywell average air temperature shall not exceed 135 F.

APPLICABILITY:

OPERATIONAL CONDITIONS l, 2'nd 3.

ACTION:

With the drywell average air temperature greater than l35'F, reduce the average air temperature to within the limit within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE RE UIREMENTS 4.6.1.7 The drywell average air temperature shall be=the arithmetical average of the higher temperature at a minimum of 3 of the following elevations and shall be'etermined to be within the limit at least once per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

Elevation a.

797'8" b.

752'2" c.

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'USQUEHANNA

- UNIT 1 3/4 6"10

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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of PENNSYLVANIA POWER LIGHT COMPANY Docket No. 50-387 AMENDMENT NO.

15 FACILITY OPERATING LICENSE NO. NPF-14 SUSQUEHANNA STEAM ELECTRIC STATION UNIT NO.

1

Licensee, Pennsylvania Power

& Light Company, hereby files Amendment No.

15 to its Facility Operating License No. NPF-14 dated July 17, 1982.

This amendment contains revisions to Appendix A of License No. NPF-14, the Susquehanna SES Unit One Technical Specifications.

PENNSYLVANIA POWER

& LIGHT COMPANY BY:

N.

W. Curtis Vice President Engineering and Const:ruction

Nuclear, Swor~p an/ subgcriPed before me this ~W~QQJf, 1982.

f'otary public iu Arly t".'BAR~)0, Botaiy t'UbilIC Allentown'~ Lehigh County, Pa.

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ML17139B235

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