Text

Amend 93 to License NPF-3,changing Tech Specs to Revise Immediate Reporting Requirements & Incorporate New Reporting Sys for Significant Events.Tech Specs Should Be Reviewed Re Fire Protection Reporting Requirements
	ML20206H585
Person / Time
Site:	Davis Besse
Issue date:	04/08/1986
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Toledo Edison Co, Cleveland Electric Illuminating Co
Shared Package
ML20206H592	List: ML20206H585; ML20206H604;
References
	NPF-03-A-093 NUDOCS 8606260208
	Download: ML20206H585 (33)
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o UNITED STATES

[

NUCLEAR REGULATORY COMMISSION

<E WASHINGTON, D. C. 20SSS

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TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET N0. 50-346 DAVIS-BESSE NUCLEAR POWER' STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. NPF-3 1.

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

A.

The application for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated December 16, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and 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 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 Part 51 of the Commission'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 0perating License No. NPF-3 is hereby amended to read as follows:

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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 93, are hereby incorporated in the license. The Toledo Edison Company 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 list /'

oh F. Stolz, Directo W Project Directora

6 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 8, 1986 l

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ATTACHMENT TO LICENSE AMENDMENT N0. o, FACILITY OPERATING LICENSE NO. NPF-3 DOCKET N0. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are ioant fied by Amendment number and contain a vertical line indicating the area o'

'ange. The corresponding

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overleaf pages are also provided to maintain uocument, completeness.

Remove Insert I

I 1-2 1-2 3/4 3-52 3/4 3-52 3/4 4-20 3/4 4-20 3/4 6-9 3/4 6-9 3/4 6-32 3/4 6-32 3/4 7-38 3/4 7-38 3/4 7-42 3/4 7-42 3/4 7-47 3/4 7-47 6-7 6-7 6-10 6-10 6-12 6-12 6-14a 6-14a 6-16 6-16 6-17 6-17 6-17a 6-17a 6-18a 6-18a o

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INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS

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D E F I N E D T E RMS..............................................

1-1 THERMAL P0WER..............................................

1-1 RATED THERMAL P0WER................................~........

1-l' OP E RATI ONAL M0DE..,......................................'..

1-1 ACTION.....................................................

l.-l OPERABLE - OPERABILITY.....................................

1-1 R EP O RTAB L E EV E N T..........................................

1-2 l

CONTAINMENT INTEGRITY......................................

1-2 CHANNEL CALIBRATION........................................

1-2 CHANNEL CHECK..............................................

1-2 CHANNELFUNCTIONALTE5T...................................$

1-3 CORE ALTERATION............................................

1-3

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SHUTDOWN MARGIN............................................

1-3 I DE NT I FI ED L EA KAG E.........................................

1-3 UN I DE NTI FI ED LEA KAG E..................................... -.

1-4 PRESSURE BOUNDARY LEAKAGE..................................

1-4 CONTROLLED LEAKAGE.........................................

1-4 QUADRA NT P OWER TI LT........................................

1-4 DOSE EQUIVALENT I-131......................................

1-4 E-AVERAGE DIS INTEG RATION ENERGY............................

1-4 STAGG,ERED TEST BASIS........'...............................

1-5 FREQUENCY N0TATION.........................................

1-5 AXIAL POWER IM3ALANCE......................................

1-5 SHIELD BUILDING INTEGRITY..................................

1-5 REACTOR P ROTECTION SYSTEM RESPONS E TIME........'............

1-5 SAFETY FEATURE RESPONSE TIME...............................

1-6 PHYSICS TE5TS..............................................

1-6 STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIME...

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S O UR CE CH E CK...............................................

A -6a PROCES'S CONTROL PR0 GRAM.................................

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DAVIS-8dsSE, UNIT i 1

Amendment No. ;Er, p8', 93

t INDEX

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DEFINITIONS SECTI0ft PAGE 1.0 DEFINITIO!!S (Continued)

SOLI DI FI CATI ON........................................ 1-6a I

0FFSITE DOSE CALCULATION 11ANUAL (0DC!!)................1-6a GASEOUS RADWASTE TREATliENT SYSTEM.....................

1-6a VENTILATION EXHAUST TREATl!ENT SYSTE!1..................1-6a t

I PURGE-PURGING.........................................

1-Gb VEllTING...............................................

1-6b NEMBER(S ) 0F THE PUB LIC...............................

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SITE B00NDARY.........................................

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UtlRESTRI CTE D AREA.....................................

1-6b DE',fATER I N G............................................

l.-6b OPERATIO!!AL H0 DES (TABLE 1.1 ).........................

1-7 FREQUENCY NOTATION (TABLE 1.2)........................

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DAVIS-BESSE, UNIT 1 la Amendment No. 85

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4 1.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.

I THERMAL POWER 1.2 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

RATED THERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2772 MWt.

OPERATIONAL MODE 1.4 An OPERATIONAL MODE shall correspond to any one inclusive combina-tion of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.

ACTION 1.5 ACTION shall be those additional requirements specified as corollary statements to each principle specification and shall be part of the specifications.

OPERABLE - OPERABILITY 1.6 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when. it is capable of performing its specified function (s).

Implicit in this definition shall be the assumption that all necessary attendant instrumentation, c'ontrols, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment, that are required for the system, subsystem,' train, component or device to perform its function (s), are,also capable of performing their related support function (s). ' Prior to entering MODE 1 for Cycle 5, auxiliary feedwater s'ystem OPERABILITY shall be determined without consideration of the status of the startup feedwater system.

DAVIS-BESSE, UNIT 1 1-1 Amendment No. 82 l

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DEFINITIONS REPORTABLE CVEg 1.7 A REPORTABLE EVEtiT shall be any of those corrditionrc pecified s

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in SECTION 50.73 to 10-CFR Part 50.'

CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:

All penetrations required to be closed during accident con-a.

ditions are either:

1.

Capable of being closed by the Safety Features Actuation System, or 2.

Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-2 of Specification 3.6.3.1.

e b.

' All equipment hatches are closed and sealed, Each airlock is OPERABLE pursuant do Specification 3.6.1.3, c.

d.

The containment leakage rates are within the limits of Specification 3.6.1.2, and The sealing mechanism associated with each penetration (e.g.,

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welds, bellows or 0-rings) is OPERABLE.

CHANNEL CA'IBRATION 1.9 A CAANNEL CALIBRATION shall be the adjustment, as necessary, of the channel ou.tput such that it. responds with necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall en~ compass the entire channel including the sensor and i

alann and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.

CHANNEL CALIBRATIOC may be performed by any' series of sequential, over-lapping or total channel steps such that the entire channel is calibrated.

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CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of chahnel behavior during operation by observation. This determination shall. '

include, where possible, comparison of the channel indication and/or stat'us with oth,er indications and/or status derived from independent instrument channels measuring the same parameter.

1-2 Amendment No. 93

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4 INSTRUMENTATION _

CHLORINE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION The chlorine detection system with the ala'm/ trip setpoint adjusted to actuate at a chlorine concentration of < S ppm, shall be

3. 3. 3. 7 OPERABLE with at least two OPERABLE chlorine detectTrs located Reactor Control Room ventilation air intake.

APPLICABILITY: 1,2,3andd ACTION _:

With one chlorine detector or the. chlorine detection systen inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of a.

the control room ventilation system in the recirculation mode of operatforr, restore the inoperable detection system orleast

. detector to OPEP/SLE status within 30 days or be in a within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

The provisions of Specification 3.0.4 are not applicable.

b.

N SURVEILLANCE REQUIREMENTS The chlorine detection system shall be demonstrated OPERABLE by performance of ~a CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a CHAP.N 4.3.3.7 FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION least once per 18 months.

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3/4 3-51 DAVIS-BESSE, UNIT.1 G

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i INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8' As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-14 shall be OPERA 3LE.

APPLICABILITY:

Whenever equipment in that fire detection zone is required to be OPERABLE.

ACTION:

With the number of OPERABLE fire detection instrument (s) less tha the minimum number OPERABLE requirement of Table 3.3-14:

Within I hour establish a fire watch patrol to inspect the a.

accessible zone (s) with the inoperable instrument (s) at least once per hour, and '~

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b.. Restore the inoperable instrument (s) to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission the action taken, the cause of the inoperability and the p

.and schedule for restoring the instrument (s) to -OPERABLE status.

Ihe provisions of Specifications 3.0.3 and 3.0.4 are not c.

applicable.

SURVEILLANCE REQUIREMENTS 1

4.3.3.8.1 Each of the above required accessible fire detection instruments shall-be demonstrated OPERABLE at least once per. 6 months by performance of a CHANNEL. FUNCTIONAL TEST. Each of the above required inaccessible fire. detection instrument shall be demonstrated OPERABLE at least once per 18 months by performance of a CHANNEL FUNCTIONAL TEST.

4.3.3.8.2 The NFPA Code 72D Class A supervised circuits supervision associated with the de.tector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

4.3.3.8.3 The non-supervised circuits between the local panels in Specification 4.3.3.8.3 and the control room shall be demonstrated OPERABLE at least once per 31 days.

l DAVIS-BESSE, UNIT 1 3/4 3-52 Amendment No. JK )4 93 i

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TABLE 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS SAMPLE AND PARAMETER ANALYSIS FREQUENCY DISSOLVED OXYGEN

At least once each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months CHLORIDE At least once each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months FLUORIDE At least once each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Not required with T

< 250*F.

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' REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR_ OPERATION _

3.4.8 The specific activity of the primary coolant shall be limited to:

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0.uti/ gram DOSE EQUIVALENT I-131, and a.

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1 00/E pCi/ gram b.

1 APPLICABILITY: MODES 1, 2, 3, 4 and 5.

ACTION:

MODES 1, 2 and 3*.

f With the specific activity of the primary coolant > 1.0 pCi/ gram a.

DOSE EQUIVALENT I-131 but within the allowable limit (below and to the left of the line) shown on Figure 3.4-1, operation may i

continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months provided that cperation under these circumstances shall not exceed 10%'of the unit's total yearly -

j operating time. The provisions of Specification 3.0.4 are not applicable.

b.

With the specific activity of the primary coolant > 1.0 pCi/ gram

. DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous' time interval or exceeding the limit line shown on Figure 3.4-1, be in at least NOT STANDBY with T,yg < 530'F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

I With the specific activity of the primary coolant > 100/E c.

uC1/ gram, be in at least HOT STANDBY with T"V9< 530*F l

within 6 hcurs.

l MODES 1, 2, 3, 4 and 5:

'a.'

With the specific activity of the primary coolant > 1.0 uti/ gram DOSE EQUIVALENT I-131 or > 100/E pCi/ gram, perform the sampling and analysis requirements of item 4 a) of Table 4.4-4 until the specific activity of the primary coolant is restored to within its. limits.

If a Report is required per 10 CFR 50.73, it shall contain the results of the specific activity analyses along with l

the following:

With T,yg >_ 530*F.

DAVIS-BESSE, UNIT 1 3/4 4-20 Amendment. No. 93 o

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CONTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR O'PERATION I

3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY: H0 DES 1, 2, 3 and 4.

l ACTION:

With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing ~the Reactor Coolant System temperature above 200'F.

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SURVEILLANCE REQUIREMENTS l

4.6.1.6 The structural integrity of the containment vessel shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the accessible interior and exterior surfaces of the vessel and verifying no apparent changes in. appearance of the surfaces or other abnormal degradation. Any abnorum1 degrada~ tion of the containment vessel detected during the above required inspections-shall be reported to the' Commission.

DAVIS-BESSE, UNIT 1 3/4 6-g Amendment No. 93 o

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l-CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM l

LIMITING CONDITION FOR OPERATION 3.6.1.7 The containment purge supply and exhaust isolation valves shall

-be closed.

APPLICABILITY: Modes 1, 2, 3 and 4.

ACTION:

With any containment purge supply 'and/or exhaust isolation valve open and providing access to the outside atmosphere, operation may continue, pro-vided that the accumulated time is < 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months for the preceeding 365 days; otherwise, be in'at least HOT STAN0HY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.7 The accumulated time any containment purge supply and/or exhaust valve is open and provides access to the outside atmosphere shall be determined at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

DAVIS-BESSE, UNIT 1 3/4 6-10 I

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CONTAINMENT SYSTEMS 4

SHIELD BUILDING INTEGRITY

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LIMITING CONDITION FOR OPERATION f'

3.6.5.2 SHIELD BUILDING INTEGRITY shall be maintained.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTIONi Without SHIELD BUILDING INTEGRITY, restore SHIELD BUILDING INTEGRITY within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

i SURVEILLANCE REQUIREMENTS 3

4.6.5.2 SHIELD BUILDING INTEGRITY shall be demonstrated at least once; per 31 days by verifying that airtight doors and the blowout panels listed in Table 4.6-1 are closed except when the airtight doors are being used for normal transit entry and exit.

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5 CONTAINMENT SYSTEMS SHIELD BUILDING STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION i

3.6.5.3 The structural integrity of the shield building shall be maintained at a level. consistent with the acceptance criteria in Specification 4.6.S.3.

APPLICABILITY: MODES 1, 2, 3 and 4.

l ACTION:

With the structural integrity of*the shield building ~not conforming to i

4 the original acceptance standards, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above ~200*F.

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SURVEILLANCE REQUIREMENTS s 4.6.5.3 _The structural integrity of the shield building shall be deter-mined during the shutdown for each Type-A containment leakage rate test -

(reference Specification 4.6.1.2) by a visual inspection of the accessible interior and exterior surfaces of the shield building and verifying no l

apparent changes in appearance of the concrete surfaces or other abnormal degradation. Any abnormal. degradation of the shield building detected during th'e above required inspections shall be reported to the Cannissica.

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.

With a half-life greater than 30 days (excluding Hydrogen 3)and 1

2.,

In any form other than gas, b.

Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous six months. Sealed sources and fission detectors transferred without a certifi-cate indicating the last test date shall be tested prior to being placed into use.

, c.

Startup sources and fission detectors - Each sealed startup

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source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

4.7.8.1.3 Reports - A report shall be prepared and submitted to the Commission on.an annual basis if sealed source or fission detector leakage tests reveal the presence of > 0.005 microcuries of _ removable contamination.

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, PLANT SYSTEMS 3/4.7.9 FIRE SUPPRESSION SYSTEMS i

FIRE SUPRESSION WATER SYSTEM i

LIMITING CONDITION FOR OPERATION 3.7.9.1 The fire supression water system shall be OPERABLE with; Two 'high pressure pumps, each with a capacity of 2500 gpm, a.

with their discharge aligned to the firs suppression header.

b'.

. Separate water supplies, each' with a minimum contained volume of 250,000 gallons, and c.'

An OPERABLE flow path capable of taking suction from the Intake Forebay a.nd the Ef re Water Storage Tank and transferring the

~ water through distribution.pi, ping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves and the first valve head of the water flow alarm device on each sprhklar hose standpipe or spray system riser required tt, be OPERABLE per Specifications 3.7.9.2 and 3./.9.3.

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APPLICABILITY:' At all times.

ACTION:

With one pump and/or one water supply inoperable, restore the a.

inoperable equipment to OPERABLE status within 7 days, prepare-and submit a Special Feport to the Commissior: pursuant to Specification 6.9.2 within the next 30 days outlining the pleas-and procedures to be used to provide for the loss of redundancy in this system. The provisions of Specifications 3.0.3 and j

3.0.4 are not applicable.

b.

With the fire suppression water system otherwise inoperable:

1.

Establish a backup fire suppression water system within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and 2.

Submit a Special Report in accordance with Specificaticn 6.9.2; a)

By telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , l

b)

Confir=ed by telegraph, mailgram or facsimile trans-mission no later than the first working day following the event, and

. DAVIS-BESSE, UNIT 1 3/4 7-38 Amendment No. [ 93 i

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i b.

At least once per 92 days by veriffing that the specific gravity is appropriate for continued service of the battery.

c.

At least once per 18 months by verifying that:

1.

The batteries, cel.1 plates and battery racks show no visual indication of physical damage or abnormal deterioration, and 2.

The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

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DAVIS-BESSE, UNIT 1 3/4 7-41 Amendment No. 9.

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i PLANT SYSTEMS SPRAY AND/OR SPRINKLER SYSTEMS LIMITINGCONDITIONFOROPERATkON 3.7.9.2 The following spray and/or sprink1'er systems shall be OPERABLE:

a.

Diesel Generator Day Tank Rooms 320A and 321A b.

Diesel Generator Rooms 318 and 319 APPLICABILITY: Whenever equipment in the spray'/ sprinkler protected areaIs is required to be OPERABLE.

ACTION:

t a.

With one or more of the abov.e required spray and/or sprinkler systems inoperable, establiih a continuous fire watch with backup fire suppression equipment for the unprotected ares (s)

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within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; restore the sys. ten.to.ORERABLE status within 14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable

'.spAV[ILLANCEREQUIREMENTS 4.7.9.2 Each of the above required spray and/or sprinkler systems shall be demonstrated OPERABLE:

a.

At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

b.

At least once per 18 months:

1.

By performing a system functional test which includes simulated automatic actuation of the system, and:

a)

Verify that the automatic valve' in the,' flow" s

path ' actuate to their correct posittens on a

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test signal, and DAVIS-BESSE, UNIT 1 3/4 7-42 Amendment No. JP,93 l

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j PLANT SYSTEMS 3/4.7.10 FIRE BARRIER PENETRATIONS LIMITING CONDITION FOR OPERATION 3.7.10 All fire barrier penetrations (including cable penetration barriers, fire doors and fire dampers) in fire zone boundaries protecting safety related areas shall be functional.

APPLICABILITY: At all times.

ACTION:

With one or more of the above required fire barrier penetrations a.

non-functional, within one hour either, establish a continuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one side of the non-functional fire barrier and establish an hourly fire watch patrol. Restore the non-functional fire barrier penetration (s) to functional status within 7 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the non-functional penetration and plans and schedule for restoring the fire barrier penetration (s) to functional status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.10 The above required penetration fire barriers shall be verified to be functional:

a.

At least once per 18 months by a visual inspection, b.

Prior to returning a penetration fire barrier to functional status-following repairs or maintenance by performance of a visual inspection of the affected penetration fire barrier (s).

DAVIS-BESSE, UNIT 1 3/4 7-47 Amendment No. 7, $),93 4-

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ADMINISTRATIVE CONTROLS Review of all. proposed changes to Appendix "A" Technical c.

Specifications.

d.

Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

Investigation of all violations of the Technical Specificatient e.

including preparation and forwarding of reports covering evalua-tion and. recernendations to prevent recurrence to the Vice President - Nuclear and to the Chainnan of the Comoany Nuclear Review Board.-

f.

Review of all REPORTABLE EVENTS.

l Review of facility operations to detect potential safety g.

hazards.

h.

Performance of special reviews, investigations and analyses and recorts thereon as recuested by the Chair =an of the Com;any Nuclear Review Board, i.

Review of the Plant Security Plan and implementing precedures and shall submit recomended changis to the Chairman of tne Company Nuclear Review Board.

Review o"f the Emergency Plan and implementing procedures and J.

s. hall submit ~recomended changes to the Chairman of the Company Nuclear Review Board.

k.

Review of any unplanned, accidental or uncontrolled radioactive releases, evaluation of the event, ensurance that remedial action is f(entified to prevent recurrence. review of a report covering the' evaluation and forwarding of the report to the Station Superintendent and to the CNRS.

1.

Review of the CFFSITE DOSE CALCULATION MANUAL and implementation of procedures at least once per 24 months.

Review of the PROCESS CONTROL PROGRAM and implementation of a.

procedures for prccessing and packaging of radioactive wastes at

.least once per 24 months.

Review of the Annual Radiological Environmental Operating n.

Report.

Review of'the Semiannual Radioactive Effluent Release Report.

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l DAVIS-BESSE. UNIT 1 6-7 Amendment No. 27.)(.93 i

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1 NDMINISTRATIVECONTROLS AUTHORITY

6. 5.1. 7 The Station Review Board shall:

Recommend to the Station Superintendent written approval or a.

disapproval of items considered under 6.5.1.6(a) through (d) above.

b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety' question.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice c.

President, Nuclear and the Company Nuclear Review Board of disagreement between the SRB and the Station Superintendent; however..the Station Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The Station Review Board shall maintain written ninutes of 1ach meeting and copies shall be provided to the Vice President. Nuclear and Chairman of the Company Nuclear Review Board.

6.5.2 COMPANY NUCLEAR REVIEW BOARD (CNRB)

FUNCTION 6.5.2.1 The Company Nuclea'r Review Board (CNRB) shall function to provide independent review and audit of designated activities in the areas of:

Nuclear power plant operations.

a.

b.

Nuclear engineering.

c.

Chemistry and radicchemistry.

d.

Metallurgy, Instrumentation and control,-

e.

f.

Radiological safety, g.

Mechanical and electrical 2ngineering, and h.

Quality assurance practices.

Amendment No. h7, 86 DAVIS-BESSE, UNIT 1 6-8 r

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I ADMINISTRATIVE CONTROLS COMPOSITION

.The Company Nuclear Review Board shall be composed of the:

6.5.2.2 Director, Fossil Tacilities Engineering and Construction General Superintendent, Transmission and Substations Chairman:

Member:

' ' Superintendent, Davis-Besse Station Member:

. Director, Nuclear Services Member:

Director. Quality Assurance General superintendent, Tossil Generation facilities Member:

Member Director Nuclear Safety Member:

Director, Nuclear Facility Engineering others as deemed advisable by the CNRB Chairman

Member:

, Member:

ALTERNATES All alternate members shall be appointed in writing by the CNRS Chairman to serve on a temporary basis-however, no more than two alter-6.5.2.3

~

nates shall participate as voting members in,CNRB activities at any one time.

CONSULTANTS Consultants shall be utilized as determined by the CNRB 6.5.2.4 Chairr.an to provide expert advice to the CNRB.

HEETING FRE00ENCY The CNRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and 6.5.2.5 at least once per six months thereafter.

+

000 RUM A qucrum of CNRS shall consist of the Chairr.an or his 6.5.2.6 designated alternate and at least half of the appointed CNR3 meders No more than a minority of the ouorum s'211 r

or their alternates.

have line responsibility for operation of the facility.

i

0thers as deemed advisable by the CNRS chairman, who are appctnted to the Company Nuclear Review Board shall have an academic degree in an Engineering or Ph'ysical Science Field; and in addition, shall have

~

a minimum of five years of technical experience, of which a minimum of three years shall be in one or more of the areas specified in Specification 6.5.2.1.

DAVIS-BESSE, UNIT 1 6-9 Amendment No. 70,17. 76 i

a

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i ADMINISTRATIVE CONTROLS REVIEW 6.5.2.7 The Company Nuclear Review Board shall review:

The safety evaluations for 1) changes to procedures, equipment a.

t or systems and 2) tests or experiments completed under the l

provision of Section 50.59,10 CFR, to verify that such actions l

did not constitute an unreviewed safety question. -

b.

Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59,10 CFR.

Proposed tests or experiments which involve an unreviewed c.

safety question as defined in Section 50.59, 10 CFR.

d.

Proposed changes in Technical Specifications or this Operating License.

Violations of codes, regulations, orders, Technical Specifications, e.

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

i Significant' operating abnormalities or deviations from normal f.

and expected performance of plant equipment that' affect nuclear-i safety.

l 9-ALL REPORTABLE EVENTS.

h.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.

1.

Reports and meetings minutes of the Station Review Board.

i DAVIS-BESSE, UNIT 1 6-10 Amendment No. 93

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ADMINISTRATIVE CONTRO.S AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the CNRB. These audits shall encompass:

The conformance of unit operation to provisions contained within a.

the Technical Specifications and applicable license conditions at least once per 12 months.

b.

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

The results of actions taken to correct deficiencies occurring in c.

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

The Station Emergency Plan and implementing procedures at least e.

once per 12 months.

f.

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

9 Any other area of facility operation considered appropriate by the CNRB.

h.

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

1.

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

j.

An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

k.

The performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975 at least once per 12 months.

DAVIS-BESSE, UNIT 1 6-11 AmendmentNo.J/l,7[,J4,86 g

' ADMINISTRATIVE CONTROLS AUTHORITY 6.5.2.9 The Company Nuclear Review Board shall report to and advise the President and Chief Operating Officer on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS 5.5.2.10 Records of Comoany N.uclear Review Board activities shall be prepared, approved and distributed as indicated below:

Minutes of each CNRB meeting shall be prepared, approved a.

and forwarded to the President and Chief Operating Officer and CNR3 members within 14 days following each meeting.

.b.

Reports of reviews encommassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the President and Chief ODeratin~g Officer and CNR3 memoers within 14 days following comoletion of the review.

. Audit-reports encemmassed by Section 6.5.2.8 above, shall be c.

fcrwarded to.the. President and Chief Operating Officer and CNRB members and to the management positions responsible

- for the areas audited within.30 days after comoletion of tne audit.

d.6 REFGITABLE EVENT ; ACTION' 6.6.1 The following actions shall be taken for REPORTAELE ifENTp;(, ' "

a..

The Comnission shall be notified and/or a report submitted pursuant to the requirements of SECTION 50.73 to 10 CFR PART 50, and 8

b.*

Each REPORTABLE EVENT shall be reviewed by the SRB, and the results cf this review shall be submitted to the CNRS and the Vice President, Nuclear.

l DAVIS-BESSE, UNIT 1 6-12 Amendment No. /1, 77,-SS, 93

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ADMINISTRATIVE CONTROLS l

1 6.8.4 (Cont.)

c.

Post-Accident Sampling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive fodinas and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

(i)

Training of personnel, (ii)

Procedures for sampling and analysis, (iii)

Provisions for maintenance of sampling and analysis equipment.

6.9 REPORTING REOUIREMENTS ROUTINE REPORTS

6. 9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the appropriate Regional Office unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testin shall' be submitted following (1) receipt of an operating license, (2) g amendment to the licensee involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured bf a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.

6.9.1.2 The report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the orierating conditions ~ or characteristics 'obtained during the test program an'd a comparison of these values with design predictions and specifica-

.tions. Any corrective actions that were required to obtain satisfactory operation shall also.be described. Any additional specific details required in license conditions based on other comitments shall be in-cluded 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 resumption or comencement 'of comercial power operation, or (3) 9 months following initi.al criticality, whichever 1s earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or comencement of commercial DAVIS-BESSE, UNIT 1 6-14a AmendmentNo.77,pI.93

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ADMINISTRATIVE CONTROLS power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

E I

ANNUAL OPERATING REPORT Annual reports covering the activities of the unit during the 6.9.1.4 previous calendar year shall be submitted prior to March 31 of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

A tabulation on an annual basis of the number of station, utility a.

and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their agociated man rem exposure according to work and job functions,. e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (described maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter. TLD, or film badge measurements. Small exposures totalling.less than 20% of the individual. total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

The complete results of steam generator. tube inservice inspections b.

(Specification 4.4.5.5.b).

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics, shutdown experience and challenges to the Pressurizer Power Operated Relief Valve (PORV) and the Pressurizer Code Safety Valves shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory 20555, with a copy to the Regional Office, to Commission Washington, D.C.

arrive no later than the 15th of each month fo1N%g the calendar month covered by the report.

The M

A single submittal may be made for a multiple unit station.

submittal should combine those sections that are common to all units at the station.-

-I This tabulation supplements the requirements of.620.407'of 10 CFR Part 20.

DAVIS-BESSE, UNIT 1 6-15 Amendment No. 7. Ji, (T. 57, 77,87 r

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i DAVIS-BESSE, UNIT.1 6 16 Amendmentt/o,g,{7.93

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.ADf!INISTRATIVE CONTROLS i

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.10 Routine Radiological Environmental Operating Reports covering the operation of the unit'during the previous calendar year shall be submitted prior to Ma'y 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.

~

The Annual Radiological Environmental Operating Reports shall include summaries', interpretations, and an analysis of trends of the results of the rad.iological environmental surveillance activities for the report period, including a comparison.with, the'preoperational studies, with operational controls,~ as appropria~te, and with previous environmental surveillance ritpo'-ts and an assessment of the observed impacts of the plant operation on the. environment..The reports shall also include the results of land use' censuses required by Specification 3.12.2.

The Annual Radiological Environmental Operating Reports shall include the results of analysis'of all radiological environmental samples and of all environmental radiation 'neasurements taken during the period pursuant to the locations s'pecified in the Table and Figuies in the 00CM, as well as summar-i l

iz~ed and' tabulated results of these analyses and measurements. In the event that some individual results are not available for inclusion with the report, "

the report shall 6e submitted ~ noting and explaining the reasons for the missing results.. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental sonitoring program; at least two legible maps covering all sampling locations keyed to's tchie giving distances and directions from the centerline of one reactor; the results of licensee participation in the Intkrlaboratory Comparison Program, required by Specification 3.12.3; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

i DAVIS-BESSE, UNIT 1 6-17a Amendment No. 55,93

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DAVIS-BESSE, UNIT 1 6-17 Amendment No. E, H.

g, g3

' ADMINISTRATIVE CONTROLS G.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

Records and logs of facility operation covering time interval a.

at each power level.

b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c.

ALL REPORTABLE KVENTS.

d.

Records of surveillance, activities, inspections and calibrations required by these Technical Specifications.

4 4'

f I

k.

DAVIS-DESSE, UNIT 1 6-18a Amendment No. M. 93

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sumnuiHA11VE cr JROLS

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j SPECIAL REPORTS I

1 6.9.2 Special reports shbil be' submitted to the Director of the Office bf Inspection and Enforcement Regional Office within the time pgriod hpe,cified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

ECCS Actuation, Spec' fications 3.5.2 and 3.5.3.

a.

i i

b.

Inoperable Seismic Honitoring Instrumentation, Spect'fication 3.3.3.3.

Inoperable Meteorological Monitoring Instrumentation, c.

Specification 3.3.3.4.

d.

Seismic event andlysis, Specification 4.3.3.3.2.

Fire Detection Instrumentation Specification 3.3.3.8.

e.

f.

Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2.

Fire Barrier Penetrations, Specificatfor. 3.7.10.

_g.

h.

Dose or dose connitment exceedences to a ME!!BER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (Specification 3.11.1.2).

1.

The discharge of radioactive liquid waste without treatment i

and in excess of the limits in Specification 3.11.1.3.

J. - The calculated air dose from radioactive gases exceeding the limits in Specification 3.11.2.2.

k.

The calculated dose from the release of iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding the limits in Speciftcation 3.11.2.3.

1.

The discharge of radioactive gaseous waste without treatment and in excess of the limits in Specification 3.11.2.4.

The calculated doses from the release of radioactive materials m.

in liquid or gaseous effluents exceeding the limits in Specification 3.11.4.

The level' of radioactivity as the result of plant effluents n.

in an environmental sampling medium exceeding the reporting l

1evels of Table 3.12-2 (Specification 3.12.1).

l i

MVIS-BESSE, UNIT 1 6-18 Amendment No. 7,' JJ, SJ,86 m

ML20206H585

Text

Attachment:

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