ML20117J341

Amend 111 to License NPF-30,revising TS 1.7,4.6.1.1,3.6.1.3, 4.6.1.3,6.8.4 & Associated Bases Section to Directly Ref RG 1.163 as Required by 10CFR50,App J,Option B for Type a Cilrts & Type B & C LLRTs

ML20117J341
Person / Time
Site:	Callaway
Issue date:	05/28/1996
From:	Thomas K NRC (Affiliation Not Assigned)
To:
Shared Package
ML20117J343	List: ML20117J341 ML20117J346
References
NUDOCS 9605310096
Download: ML20117J341 (12)

Text

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k UNITED STATES e-5 j-NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. anama aaa1

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UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 DOCKET NO. 50-483 ANENDNENT TO FACILITY OPERATING LICENSE I

Amendment No. 111 License No. NPF-30 1.

The Nuclear Regulatory commission (the Commission) has found that:

A.

The application for amendment by Union Electric Company (UE, the e

licensee) dated February 9,1996, as superseded by letter dated March 22, 1996, complies with the standards and requirements.of the i

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

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

C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering' the health and 1

safety of the public, and (ii) that such activities will be conducted in compliance with 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 Ftrt 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:

i 9605310096 960520

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PDR ADOCK 05000483 P

PDR

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(2) Technical Snecifications and Environmental Protection Plan 1

The Technical Specifications contained in Appendix A, as revised through Amendment No. 111 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

i The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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3.

This unendment is effective as of its date of issuance to be implemented within 30 days of the date of issuance.

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FOR THE NUCLEAR REGULATORY COMMISSION l

Oh MThoe 1

Kristine M. Thomas, Project Manager i

Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications i

Date of Issuance:

May 28, 1996 1

1

I ATTACittENT TO LICENSE AMEN 0 MENT AMENDMENT NO, 111 TO FACILITY OPERATING LICENSE NO. NPF-30 DOCKET _NO. 50-483 i

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

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The corresponding 4

overleaf pages are also provided to maintain document completeness.

l REMOVE ESERI l-l*

1-1 l-2 1-2 i

3/4 6-1 3/4 6-1 2

3/4 6-4 3/4 6-4 3/4 6-5 6-19 6-19 6-19a 6-19a 6-19b 6-19b 6-20*

6-20 B 3/4 6-1 8 3/4 6-1

• No changes were made to these pages.

Pages being reissued to become overleaf pages.

1.0 DEFINITIONS The defined tems of this section appear in capitalized type and are applicable throughout these Technical Specifications.

i ACTION 1.1 ACTION shall be that part of a Technical Specification which prescribes remedial measures required under designated conditions.

ACTUATION LOGIC TEST 1.2 An ACTUATION LOGIC TEST shall be the application of various simulated input cortinations in conjunction with each possible interlock logic state and i

verification of the required logic output.

The ACTUATION LOGIC TEST shall include a continuity check, as a minimum, of output devices.

i ANALOG CHANNEL OPERATIONAL TEST 1.3 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY cf alarm, interlock and/or trip functions. The ANALOG CHANHEL.

OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, inter-lock and/or Trip Setpoints such that the Setpoints are within the required range and accuracy.

AXIAL FLUX ulFFERENCE 1.4 AXIAL FLUX DIFFERENCE shall be the difference in normalized flux signals between the top and bottom halves of a two section excore neutron detector.

CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATIOR shall be the adjustment, as necessary,- of the chennel such that it responds within the required range and accuracy to known values of input. The CHAMIEL CALIBRATION shall encompass the entire channel including the sensors and alam, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire che 31 is calibrated.

CHANNEL CHECK 1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior i

during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

1 l

1 CALLAWAY - UNIT 1 1-1 i

DEFINITIONS j

CONTAlletENT INTEGRITY l'

l.7 CONTAlleENT INTEGRITY shall exist when:

a.

All penetrations required to be closed during accident conditions are either:

i 1)

Capable of being closed by an OPERABLE containment automatic l'

isolation valve system, er s

l 2)

Closed by manual valves, blind flanges, or deactivated automatic l

valves secured in their closed positions, except as provided in j

Table 3.6-1 of Specification 3.6.3.

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j b.

All equipment hatches are closed and sealed.

c.

Each air lock is in compliance with the requirements of Specification 1

3.6.1.3.

4 d.

The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE.

e.

The containment leakage rates are determined per Specification 4.6.1.1.d and are within the limits listed in the Containment Leakage Rate Testing Program of Specification 6.8.4.g.

f.

Structural integrity is assured via the program described in Specification 6.8.5.c.

CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be that seal water flow from the reactor coolant pump seals.

CORE ALTERATION n

1.g CORE ALTERATION shall be the movement or manipulation of any component within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATION shall not preclude completion of movement of a i

component to a safe conservative position.

CORE OPERATINE LIMITS REPORT j

1.10 The CORE OPERATING LIMITS REPORT (COLR) is the unit specific document i

that provides core operating limits for the current operating reload cycle.

The cycle specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.g.

Plant operation within these operating limits is addressed in individual specifications.

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DOSE EQUIVALENT I-131 i

1.11 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (micr0 Curie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132, I-133,1-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."

1 CALLAWAY - UNIT 1 1-2 Amendment No. M,35,5",203,111 1

f 3/4.6 CONTAIMENT SYSTEMS 3/4.6.1 PRIMARY CONTAIMENT CONTAIMENT INTEGRITY LIMITING CofEITION FOR OPERATION 3.6.1.1 Primary CONTAIMENT INTEGRITY shall be maintained.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

Without primary CONTAIMENT INTEGRITY, restore CONTAIMENT INTEGRITY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STAND 8Y 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 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a.

At least once per 31 days by verifying that all penetrations

• not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.3; b.

By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3; c.

Deleted.

l d.

By performing containment leakage rate testing in accordance with the Containment Leakage Rate Testing Program of Specification 6.8.4.g; and e.

By verifying containment structural integrity in accordance with the Containment Tendon Surveillance Program of Specification 6.8.5.c.

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• Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

CALLAWAY - UNIT 1 3/4 6-1 Amendment No.13,S:',103,111

CONTAIMENT SYSTEMS CONTAIMENT AIR LOCKS i

LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with both doors closed except when the air lock is being used for normal transit entry and exits through the containment, then at least one air lock door shall be closed.

APPLICABILIIY: MODES 1, 2, 3, and 4.

ACTION:

a.

With one containment air lock door inoperable:

1.

Maintain at least the OPERABLE air lock door closed and either i

restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed, 2.

Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days, 3.

Otherwise, 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 />, and 4.

The provisions of Specification 3.0.4 are not applicable.

l b.

With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 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 RE0VIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a.

By verifying leakage rates in accordance with the Containment Leakage Rate Testing Program of Specification 6.8.4.g; and b.

At least once per 6 months by verifying that only one door in each l

air lock can be opened at a time.

I CALLAWAY - UNIT 1 3/4 6-4 Amendment No. 43,111 (Next page is 3/4 6-6) l

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AIMINISTRATIVE CONTROLS i

PROCEDURES Als PRDGRAMS (Continued) f.

wioloaical Environmental Monitorina Proaram (Continued) i 3)

Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

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g.

Centainment Leakane Rate Testing Program 4

A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, i

Appendix J, Option B, as modified by approved exemptions. This i

ran shall be in accordance with the guidelines contained in l

ulatory Guide 1.163, "Perfonnance-Based Containment Leak-Test Program," dated September 1995.

l The peak calculated containment internal pressure for the design basis loss of coolant accident, P., is 48.1 psig.

I The maximum allowable containment leakage rate, L,, at P,, shall be l

0.20% of the containment air weight per day.

i Leakage rate acceptance criteria are:

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a.

Containment leakage rate acceptance criterion is s1.0 L '

During the first unit startup following testing in acco,rdance i

with this program, the leakage rate acceptance criteria are l

50.60 L, for the Type B and C tests and so.75 L, for Type A tests; i

b.

Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is 50.05 L, when tested at i

2P ;

2)

For each door, leakage rate is 50.005 L, when pressurized i

to 210 psig.

The provisions of Technical Specification 4.0.2 do not apply to the test frequencies in the Containment Leakage Rate Testing Program.

The provisions of Technical Specification 4.0.3 are applicable to the l

Containment Leakage Rate Testing Program.

l, 6.8.5 The following programs, relocated from the Technical Specifications to 1

FSAR Chapter 16, shall be implemented and maintained:

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a.

Exolosive Gas and Storaae Tank Radioactivity Monitorino Proaram 1

This program provides controls for potentially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM, the quantity of radioactivity contained in gas storage tanks, and the quantity of l

radioactivity contained in unprotected outdoor liquid storage tanks.

CALLAWAY - UNIT 1 6-19 Amendment No. 27,50,103,111 1

'ADNINISTRATIVE CONTROLS PROCEDURES AIET PROGRAMS (Continued) l The program shall include:

1.

The limits for concentrations of hydrogen and oxygen in the WASTE GAS HOLDUP SYSTEM and a surveillance program to ensure the limits are maintained.

2.

A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank is less than the amount that would result in a whole body exposure of it0.5 rem to a MEMBER OF THE PUBLIC at the nearest SITE BouleARY in the event of an uncontrolled release of the tanks' contents, consistent with Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases due to Waste Gas System Leak or Failure,"

in NUREG-0tE, July 1981.

3.

A surveillance program to ensure that the quantity of radioactivity contained in the following outdoor liquid radwaste tanks, that are not surrounded by liners, dikes, or walls capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste system, is less than the amount that would result in concentrations less than the limits of 10 CFR Part 20.1 -20.602, Appendix B (redesignated at 56FR23391, May 21, 1991) at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA, in the event of an uncontrolled release of the tanks' contents:

a.

Reactor Makeup Water Storage Tank, b.

Refueling Water Storage Tank, c.

Candensate Storage Tank, and d.

Outside temporary tanks, wxcluding demineralizer vessels and the liner being used to solidify radioactive waste.

The provisions of Specificati(ins 4.0.2 end 4.0.3 are applicable i

to the Explosive Gas and Storage Tank RadioRetivity Monitoring i

Program surveillance frequencies.

I b.

Reactor Coolant Pa=a Flywheel Inspection Proaram 1

}

Each reactor coolant pump flywheel shall be inspected per the i

recommendations of Regulatory Porition C.4.b of Regulatory Guide j

1.14, Revision 1, dated August 1975.

c.

Containment Tendon Surveillance Proaram This program provides controls for monitoring tendon performance, j

including the effectiveness of the tendon corrosion protection i

medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial plant operation 1

as well as periodic testing thereafter. The Containment Tendon Surveillance Program, and its inspection frequencies and acceptance 1

criteria, shall be in accordance with the Callaway position on j

proposed Revision 3 of Regulatory Guide 1.35 dated April 1979.

l CALLAWAY - tslIT 1 6-19a Amendment No. M&,111 l

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ADMINISTRATIVE CONTROLS j

PROCEDURES Als PROGRAMS (Continued) l c.

Containment Tendon Surveillance Proaram (Continued)

The provisions of Specifications 4.0.2 and 4.0.3 are applicable to j

the Containment Tendon Surveillance Program inspection frequencies.

1 6.9 REPORTING RE0UIREMENTS 1

ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code i

of Federal Regulations, the following riports shall be submitted to the l

Regional Administrator of the NRC Regional Office unless otherwise noted.

STARTUP REPORT j

6.9.1.1 A summary report of plant startup and power escalation testing shall

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be submitted following:

(1) receipt of an Operating License, (2) amendment to the License involving a planned increase in power level, (3) installation of a

fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the i

nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The Startup Report shall address each ol' the tests identified in the 1

FSAR and shall include a description of the meast, red values of the operating j

conditions or chara::teristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective 4

actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions j

based on other commitments shall be included in this report.

6.9.1.3 Startup Reports shall be submitted within:

(1) 90 days following completion of the Startup Test Program, (2) 90 days following reauemption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, j

and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been j

completed.

j ANNUAL REPORTS i.

6.9.1.4 Annual Reports covering the activities of the unit as described below i

for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year j

following initial criticality.

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i CALLAWAY - UNIT 1 6-19b Amendment No. M8,111 A,

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1 ADMINISTRATIVE CONTROLS k'

ANNUAL REPORTS (Continued) l 6.g.1.5 annual basis of the number of station, utility, and other pe

}

i t.ontractors) receiving exposures greater than 100 nrems/yr and their(including j

associated man-res exposure accordin

, reactor operations and surveillance,g to work and jeb functions, *e.g.,

s inservice inspot. tion restine maintenance, special maintenance (describe maintenaxa), w,asta process refueling. The dose assignments to various duty functhns i

based on pocket dosianter, TLD, or film badge seaturaments. be estimated i

totalling less than 205 of the individual total dese need not be accounted 11 exp for.

In the aggregate from external sources s,hould be assigned to specific major we j

which the primary coolant exceeded the limits of Specif i

j following information shall be included:

The hours pr' or to the first sample in which the limit was exceeded:(1) Reactor pow

)

of the last isotopic analysis for radiciodine performed prior to ex(ce)eding 2 Resu ts i

limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit.

i result should include date and time of sampling and the radioledine Each i

concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to i

the first sample in which the limit was exceeded;

{

concentration and one other radiciodine isotope con (ce)ntration la microcur 4 Graph of the 1-131 4

the steady-state level; and (5) The time duration when i

l of the primary coolant exceeded the radiciodine limit.

ANNUAL RADIOLOGICAL ENVIR0lelENTAL OPERATING REhWii 6.g.1.6 operation of the unit during the previous calendar year sha i

I before May I of each year. The report shall include suinnaries.

8 Environmental Monitoring Program for the reporting period.

j The material provided shall be consistent with the objectives outlined in (1) the 00CM and (2) Sections IV.8.2, IV.S.3, and IV.C of Appendix I to 10 CFR Part 50.

l ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REi;0iii 6.9.1.7 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year of operation shall be j

submitted before May I of each year.

the quantities of radioactive liquid and gasmus effluents and enlid wast a

released from the unit.

The material provided shall be 1 consistent with 50.36a and Section IV.B.I of Appendix I to 10 CFR Part 50.th f

t I

4 i

i This tabulation supplements the requirements of f 20.407 of Ig CFR

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Part 20.

i CALLAWAY - UNIT 1 6-20 Amendment No. 27, 99, 89 I

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odl

3/4.6 CMTAIMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAIMENT 3 /4.6.1.1 CONTAlW ENT INTEGRITY Primary CONTAIW elT INTEGRITY ensures that the release of radioactive

' materials from the containment atmosphere will be restricted to those leakage t

paths and associated leak rates assumed in the safety analyses. This restriction, in conjunction with the leakage rate limitation, will limit the l

SITE BOUWARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions.

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l CALLAWAY - UNIT 1 B 3/4 6-1 Amendment No. 75,77,98,100,111 l

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