ML20094L013

Amend 170 to License NPF-3,revising Tech Specs to Relocate Procedural Details of Current RETS to ODCM & PCP

ML20094L013
Person / Time
Site:	Davis Besse
Issue date:	03/09/1992
From:	Hopkins J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20094L015	List: ML20094L013 ML20094L020
References
NUDOCS 9203240068
Download: ML20094L013 (37)

Text

..

no ceog$'o UNITED STATES r

e NUCLE AR REGULATORY COMMISSION

-g WASHING TON, D. C. 20555

t y

IQLEQQ_LDISON COMPANY CENTERIOR SERVICE COMPANY l

THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET N0. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 170 License-No. NPF-3 1.

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

A.

The' application for amendment by the Toledo Edison Company, Centerior

-Service Company, and the Cleveland Electric Illuminating Company

-(the licensees) dated April 12,1991 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) thatLthe 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 l:

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 1'ssuance of this amendment is in accordance with 10 CFR Part 51 of the' Cos.aission's regulations and all applicable. requirements have been satisfied, 2.

Accordingly, the license is amended by changes to the Technical Specifications as-indicated in the' attachment to this-license amendment, and paragraph 2.C.(2)'of Facility Operating License No. NPF-3 is hereby amended to read as follows:

--9203240068 920309 PDR ADOCK-05000346 P

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4 2

(a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No 170, are hereby incorporated in the licere,,u.

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 and shall be implemented not later than 45 days after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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D i ) p.

w on B. Hopkins, Sr. Project Manaaer Project Directorate 111-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

bbrch 9, 1992 y

_. - -. - -. _ _. ~

ATTACHMENT TO llCEllSE AMENDMENT NO.170 FAClllTY OPERATING LIff8SE N0.- NPF-1 D0_C_KET NO. 50-146 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change, The corresponding overleaf pages are also provided to maintain document completeriess.

Remove inittl INDEX 1 INDEX 1 INDEX la INDEX la INDEX IV INDEX IV INDEX Villa INDEX VI!!a INDEX XIII INDEX Xill INDEX XIV INDEX XIV INDEX XVI INDEX XVI l-6a-1-6a 1-6b l-6b 1-6c 1-8 1-8 3/4 3-57 through 3/4 3-67 3/4 3-57 3/4 11-1 through 3/4 11-20 3/4 11-1 and 3/4 11-2 3/4 12-1 through 3/4 12-13 3/4 12-1 B 3/4 3-6 8 3/4 3-6 8 3/4 11-1 through 8 3/4 11-7 8 3/4 11-1

. and B 3/4 11-2 B 3/4 12-1 8 3/4 12-1 5-1 5-1 5-9 5-10 6-14a 6-14a 6-14b i

6-14c 6-17a 6-17a 6-17b

'6-17c 6-18 6-18 l

6-18a

! 19a 6-19 6-22 6-22 6-23 6-24 l

.- ~ ~

INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS DEFINED TERMS................................................

1-1 THERMAL P0n'ER................................................

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

1-1 O P E RAT I O N AL M0 D E.............................................

1-1 ACT10N.......................................................

1-1 OPERABLE - OPERABILITY.....................................

1-1 REPORTABLE EVENT........................

1-2 C ONT A I NME NT I N T E G R I T Y........................................

1-2 CHANNEL CAllBRAT10N..........................................

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

1-2 CHANNEL FUNCTIONAL TEST......................................

1-3 CORE ALTERAT10N..............................................

1-3 SHUTDOWN MARGIN..............................................

1-3 IDENTIFIED LEAKAGE...........................................

1-3 UN I DE NT I F I E D L E A KAGE.........................................

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

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

1-4 QUADRANT POWER TILT..........................................

1-4 DO S E E QU I V AL E NT l - 131........................................

1-4 T-AVERAGE DISINTE6 RATION ENERGY..............................

1-4 STAGGERED TEST BASIS.........................................

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

1-5 AXIAL POWER IMBALANCE........................................

1-5 SHI EL D BUILDI NG INTEGRITY....................................

1-5 REACTOR PROTECTION SYSTEM RESPONSE TIME......................

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

1-6 PHYSICS TESTS................................................

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

1-6 i

P ROC ES S CO NT ROL P R0G RAM......................................

1-6a DAVIS-BESSE, UNIT 1 1

Amendment No. EB, B6, 97,170 l_

~1NDEX l

DEFINITIONS SECTION PAGE 1.0 DEFINITIONS (Continued) 1 0FFSITE DOSE C ALCUL AT ION MANUAL (0DCM)........................

1-6a I

MEMB E R( S ) 0 F T HE PUBL I C.......................................

1 - 6a i

SITE B0VNDARY.................................................

1-6a I

UNRESTRICTED AREA.............................................

1-6b I

CORE OPERAT ING L IMIT S REP 0RT..................................

1 -6b l

OPERAT IONAL MODES (TABLE 1.1 ).................................

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

1-8 DAVIS-BESSE, UNIT 1 la Amendment No. EE,Jff '270

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE _RE_QU_llEMENTS SECT'ON PAGE 3/4.0 A P PL I C AB I L I T Y.............................................

3 / 4 0 - 1 3/4.1. REACTIVITY CONTROL SYSTEMS 3.4.1.1 BORAT10N CONTROL S h u t down Ma rg i n........................................

3/ 4 1 - 1 B o ro n D i l u t i o n.........................................

3 / 4 1 - 3 Moderator Temperature Coefficient.......................

3/4 1-4 Minimum Temperature for Criticality.....................

3/4 1-5 3/4.1.2 B0 RATION SYSTEMS Flow Paths - Shutdown..................................

3/4 1-6 Fl ow Pa ths - Opera ti ng.................................

3/4 1 -7 Ma keup Pump - Shu tdown.................................

3/ 4 1 -9 Makeup Pumps - Operating...............................

3/4 1-10 Decay Heat Removal Pump - Shutdown.....................

3/4 1-11 Boric Acid Pump - Shutdown.............................

3/4 1-12 Boric Acid Pumps - Operating...........................

3/4 1-13 Borated Water Sources - Shutdown.......................

3/4 1-14 Berated Water Sources - Operating......................

3/4 1-17 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height - Safety and Regulating Rod Groups........

3/4 1-19 Group Height - Axial Power Shaping Rod Group..........

3/4 1-21 Position Indicator Channels............................

3/4 1-22 Rod D ro p T ime..........................................

3/ 4 1 - 24 Sa fety Rod Insertion Limit.............................

3/4 1-25 Regulating Rod Insertion Limi ts........................

3/4 1-26 Ro d P ro g ra m............................................

3/ 4 1 - 3 0 X e n o n Re a c t i v i ty.......................................

3 / 4 1 - 3 3 Axial Power Shaping Rod Insertion Limits...............

3/4 1-34 DAVIS-BESSE, UNIT L 111 Amendment No. 3B

__ __._ ~ -.. _ _

INDEX LIMITIN3 CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3]4.2 POWER _ DISTRIBUTION LIMITS 3/4.2.1 AXIAL POWER IMBALANCE,.................................... 3/4 2-1 3/4.2.2 N'JCL EAR HEAT FLUX HOT CHANNEL FACTOR - F................. 3/4 2-5 g

N 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F3g...........

3/4 2-7 3/4.2.4 QUADRANT POWER TILT......................................

3/4 2-9 3/4.2.5 DNB PA RAMET E RS...........................................

3/ 4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION................

3/4 3-1 3/4.3.2 SAFETY SYSTEM INSTRUMENTATION Safety Features Actuation System.........................

3/4 3-9 Steam and Feedwater Rupture Control System...............

3/4 3-23 Anti ci patory Re:.ctor Trip System.........................

3/4 3-30a 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrum c.tation.....................

3/4 3-31 Incore Detectors.........................................

3/4 3-35 l

Sei smi c I ns trumenta tion..................................

3/4 3-37 Heteorological Instrumentation...........................

3/4 3-40 Remote Shutdown Ins trumenta tion..........................

3/4 3-43 Post-Accident Monitoring Instrumentation.................. 3/4 3-46 Fire Detection Instrumentation...........................

3/4 3-52 Wa ste Gas System Oxygen Monitori ng.......................

3/4 3-57 l

l 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power 0peration..............................

3/4 4-1 Shutdown and Hot Standby.................................

3/4 4-2 3/4.4.2 SAFETY YALVES - SHUTD0WN.................................

3/4 4-3 3/4.4.3 SAFETY VALVES AND PILOT OPERATED RELIEF VALVE -

0PERATING..............................................

3/4.4-4 L

DAVIS-BESSE, UNIT 1 IV Amendment No. 2B,EE,J3A,J35,47,170 l

INDEX LIMITING.' CONDITIONS-FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11 RADIDACTIVE EFFLUENTS 3/4.11.1 - L IQUI D E FFLUENTS.........................................

3/ 4 11 - 1 i

Liquid Hol dup Ta nks......................................

3/4 11-1 j

3/4.11.2 GASEOUS E F FL UENT S........................................

3/ 4 11 - 2 I

Expl os i ve Gas Mi xture....................................

3/4 11-2 l

4 DAVIS-BESSE, UNIT 1 VI!!a Amendmer,t No. P,5,170

.=

A INDEX BASES SECTION PAGE 3/4.9.6 - FUEL HANDLING BRIDGE OPERABILITY.......................... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING..................... B 3/4 9-2 3/4.9.8 COOLANT CIRCULATION....................................... B 3/4 9 2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM............ B 3/4 9-2 3/4.9.10 and-3/4.9.ll WATER LEVEL - REACTOR VESSEL AND STORAGE P00L............................................ B 3/4 9-2 3/4.9.12 STO RAGE POOL VE NT I L AT I ON.................................. B 3/4 9-3 3/4.9.13 SPENT FUEL P0OL FUEL ASSEMBLY ST0 RAGE..................... B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT. INSERTION AND POWER DISTRIBUTION LIMITS..... B 3/410-1 3/4.10.2 PHYSICS TESTS.............................................

B 3/4 10-1 3/4.10.3 REACTOR COOL ANT L00PS..................................... B 3/4 10-1 3/4.10.4 S H UT DOWN MARG I N........................................... B 3/ 4 10- 1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 L IQUI D HOL DUP TAN KS....................................... B 3/4 11 - 1 l

3/4.11.2 EXPLOSIVE GAS MIXTURE..................................... B 3/4 11-1 3/4.12 DELETED l

DAVIS-BESSE, UNIT 1 XIII Amendment No. RE.J30.JJ5.170

e INDEX DESIGN FEATURES SECTIONi PAGE 5.- 1 SITE Exclusion Area.................................................

5-1 Low Population Zone............................................

5-1 S i t e B o u n d a ry..................................................

5 l

5. 2 CONTAINMENT Configuration..................................................

5-1 Design. Pressure and Temperature.................................

5-4 5.3 -REACTOR CORE F u e l As s emb l i e s................................................

5-4 Control Rods....................................................

s-4

5. 4 REACTOR COOLANT SYSTEM' Design Pressure and Temperature................................

5-4 Volume.........................................................

5-5

5. 5 MSTEOR0 LOG ICAL TOWER LOCATION..................................

5-5 5.6 FUEL STORAGE-C r i t i c a l i ty..................................................... 5-5 D r a i n a g e.......................................................

5-5 Capacity.......................................................

5-6 5.7 COMPONENT CYCL IC OR T RANSI ENT L IMIT............................

5-6 DAVIS-BE5SE, UNIT 1 XIV Amendment No. 38,170

. ~.

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY................................................

6-1 6.2 ORGANIZATION Of fsi te and Ons i te Organiza ti ons.........................

6-1 l

F a c i l i ty S ta f f...........................................

6-l a facility Staff 0vertime..................................

6-4a l

6. 3 FAC IL ITY STAFF QUAL I F IC ATIONS.................................

6-5 6. 4 - T R A I N I N G......................................................

6-5 6.5 -REVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD F u n c t i o n.....'...........................................

6-5 C omp o s i t i o n..............................................

6-6 Al te rn a t e s...............................................

6-6 Meeting-Frequency........................................

5 Quorum.................................................... 6-6 Responsibilities'.........................................

6-6

- A u t h o r i ty................................................

6-8 l-Records..................................................

6-8 6.5.2 COMPANYLNUCLEAR REVIEW BOARD Function.................................................

6-9 Composition.............................................

6-9 Al t e rn a t es...............................................

6-9 Consultants..............................................

6-9 t

DAVIS-BESSE, UNIT:1 XV Amendment No. 38,135 m

17-INDEX ADMINISTRATIVE CONTROLS SECTION PAGE M e e t i n9 F r eq u e n cy........................................

6-9 Quorum...................................................

6-9 Review...................................................

6-10 Audits...................................................

6-11 Authority...............................................

6-12 Records..................................................

6-12 6.5.3' Technical Review and Control.............................

6-12 6.6 RE PORT ABL E E V E NT ACT I0N......................................

6-12a 6.7 SAFETY LIMIT VIOLATION........................................

6-13 6.8 P RO C E DU RE S AN D P R0GR AMS.......................................

6-13 6.9 REPORTING REQUIREMENTS 6.9.1 Routine Reports..........................................

6-14C l

6.9.2 S pe c i a l. Re por ts..........................................

6-18 6.10 RECORD RETENTION.............................................

6-1Ba l

i 6.11 RADIATION, PROTECTION PR0 GRAM.................................

6-20 1

I

! 6.12 'HIGH RADIATIONAREA..........................................

6-20 l

I 6.13 E NV I RONMENTAL - QU AL I F I CAT I ON..................................

6-21 1

6.14 PROCESS' CONTROL PROGRA" 'PCP )................................

6-22 6.15 0FFSITE DOSE CAL CUL ATION MANUAL (00CM).......................

6-22 DAVIS-BESSE, UNIT 1 XVI Amendment No. 38.I3517D

- _~

.~

DEFINITIONS 1.29 Deleted l

PROCESS CONTROL PROGRAM 1.30-ThePROCESS-CONTROLPROGRAM(PCP)shallcontainthecurrentformulas, sampling, analyses.-tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated-processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

l 1.31 Deleted OFFSITE DOSE CALCULATION MANUAL (ODCM)-

1.32 The 0FFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitorir.g Alann/ Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program.

The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Ervironmental Monitoring Programs required by Section 6.8.4 and' (2) descriptions of the intorn;ation that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by Specificacions 6.9.1.10 and 6.9.1.11.

1.33 Deleted l

1.34 Deleted 1.35 Deleted

-l-1.36-Deleted l

MEMBER (S) 0F THE-PUBLIC 1.37 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupation-ally associated with the plant. This category does not include employees of the utility, its contractors or vendors.

Also excluded from this category are persons who enter the site to service. equipment or to make deliveries.

This category does include persons who use portions of the site for recrea-tional, occupational or other purposes not associated with the plant.-

SITE BOUNDARY 1.38 The SITE BOUNDARY shall-be that line beyond which the land is neither owned, nor. leased nor otherwise controlled'by the licensee.

DAVIS-BESSE, UNIT 1 1-6a.

Amendment No, M,170

DEFINITIONS UNRESTR!CTED AREA 1.39 - An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area witnin the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. The definition of UNRESTRICTED AREA used in implementing the Radiological. Effluent Technical Specifications has been expanded over that in 10 CFR 20.3(a)(17). The UNRESTRICTED AREA boundary may coincide with the exclusion (fenced) area boundary, as defined in 10 CFR 100.3(a), but the UNRESTRICTED AREA does not include areas over water bodies. The concept of UNRESTRICTED AREAS, estab-lished at or beyond the SITE BOUNDARY, is utilized in the LIMITING CONDITIONS FOR OPERATION to keep levels of radioactive materials in liquid and gaseous-effluents as low as is reasonably achievable, pursuant to 10 CFR 50.36a.

1.40-Deleted CORE OPERATING LIMITS REPORT 1.41 The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current reload cycle.

These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification.6.9.1.7.

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

n l

DAVIS-BESSE, UNIT 1 1-6b Amendment No. E6,Jff 170

TABLE 1.1 OPERATIONAL MODES REACTIVITY

% RATED AVERI.GE COOLANT MODE CONDITION. Keff THERMAL P0WER*

TLMPERATURE 1.

POWER OPERATION

> 0.99

> 5%

> 280*F 2.

STARTUP

> 0.99

< 5%

> 280*F 3.

HOT STANDBY

< 0.99 0

> 280*F 4.

HOT SHUTDOWN -

< 0.99 0

280*f > T,yg > 200"f S.

COLD SHUTDOWN

< 0.99 0

1 200*f 6.

REFUELING **

1 0.95 0

1 140*f

• Excluding decay heat.

• • Reactor vessel head unbolted or removed and fuel in the vessel.

DAVIS-BESSE, UNIT 1 1-7

TABLE 1.2 FREQUENCY NOTATICN NOTATION FREQUENCY S-At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 6 months.*

R At least once per 18 months.*

S/V Prior to each reactor startup.

tyA Not applicable.

• In these Technical Specifications, 6 months is defined to be 184 days, and 18 months is defined to be 550 days.

DAVIS-BESSE, UNIT l-1-8 Amendment No. 37,EE,170

INSTRUMENTATION WASTE GAS SYSTEM OXYGEN LIMITING CONDITION FOR OPERATION 3.3.3.9 The Waste Gas System Oxygen monitoring shall be OPERABLE with its alarm setpoints set to ensure that the limits of Specification 3.11.2 are not exceeded.

APPLICABILITY:

During additions to the waste gas surge tank.

l ACTION:

a-With the waste gas system oxygen monitoring alarm setpoint less conservative than required by the above Specifications, declare the channel inoperable and comply with ACTION b.

b.

With the waste gas system oxygen monitor inoperable, additions to the waste gas surge tank may continue provided another method for ascertaining oxygen concentrations, such as grab sample anslysis,-

is implemented to provide measurements at least once per four (4) hours-during degassing and daily during other operations.

Exert best efforts to return the waste gas system oxygen monitor to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inopera-bility was not corrected in a timely manner.

c.

The-provisions lof Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 The waste gas system oxygen monitor shall be demonstrated OPERABLE by:

a.

Performance _of a CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during additions to the waste-gas surge tank.

b.

At least once per 92 days by performance of a CHANNEL CALIBRATION.

The CHANNEL CALIBRATION shall _ include the use of standard gas samples containing a nominal:-

1.

One-volume percent oxygen, balance nitrogen; and 2.

Four volume percent oxygen, balance nitrogen.

i.

DAVIS-BESSE, UNIT 1 3/4 3-57 Amendment No. EE,170

4 RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS *

, LIMITING CONDITION FOR OPERATION 3.11.1 The quantity of radioactive material contained in each of the j

following unprotected outdoor tanks shall be limited to less than or equal to 10 curies, excludinn tritium and dissolved or entrained noble gases.

a.

Outside temporary tank.

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the event leading to this condition in the next Semiannual Radio-active Effluent Release Report.

b.

_The provisions of Specifications 3.0.3 and 3.0.4 are not

applicable.

SURVEILLANCE REQUIREMENTS 4.11.1 The quantity of radioactive material contained in each of the i

above listed-tanks shall be determined to be within the ab.re limit by analyzing a representative sample of the tank contents at least once per 7 days when radioactive materials are being added to the tank.

~

• Tanks included in this specification are those outdoor tanks that 2*e not surrounded by liners, dikes, or walls-capable of' holding the tank contents or that do-not have tank overflows and surrounding area drains connected to1the liquid radwaste treatment system.

t DAVIS-BESSE, UNIT 1 3/4 11-1 Amendment No. 86,170

l RADIDACTIVE EFFLUENTS.

EXPLOS1VE GAS MIXTURE (Hydrogen rich systems not designed to withstand a bydrogen exliWi~o~nT~

LIMITING CONDITION FOR OPEP,ATION 3.11.2 The concentration of oxy 92n in the waste gas system shall be j

limited to less than or equal to 2% by volv.ne whenever the hydrogen concentration exceeds 4% t,y volume.

APPLICABillTY:

At all times.

A_CT 10'l:

6.

With the concentration of oxygen in the waste gas system greater than 2% by volume but less than or equal to 4*i by volume, reduce tN oxygen concentratton to thc above limits, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, b.

With the concentratio", of oxygen in the waste gas system greattr than 4% by volume and N hydrogen concentration greater than 4'l by volume, innediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% by volume without delay.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2 The concentrations of oxygen in the w6ste gas system shall be I

determined to be within the above limits by monitoring the waste gases in the waste gas system as required by Table 3.3-16 of Specification 3.3.3.9.

DAVIS-BESSE, UNIT 1 3/4 11 2 Amendment No. PJ, 170

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e ljiSTRUMENTATION BASES 3/4. 3. 3. 9 WASTE GAS _ SYSTEM OXYGEN MONITOR l

i

' The waste gas system oxygen monitor is provided to monitor oxygen concentra-tion of gaseous radwaste being admitted to the waste gas surge tank. Oxygen concentration is monitored to ensure that the concentration of potentially 3

explosive gas mixtures contained in the waste gas treatment system is main-tained below the flammability limits of hydrogen with oxygen.

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DAVIS-BESSE, UNIT 1 B 3/4 3-6 Amendment No. f 6,170

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3/4.11._1 LIQUID HOLDUP TANKS l

l Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the i

tanks' contents, the resulting concentrations would be less than the limits of l

10 CFR Part 20. Appendix B, Table 11 Column 2, at the nearest potable water 25Ucply.and the nearest surface water supply in an unrestricted area.

3/4.1,1. 2 EXPLOSIVE _ GAS MIXTUkt This specification is provided to ensure that the concentration of pctentially explosive gas mixtures contained in the waste gas treatment system is main-i tained below the flammability limits of hydrogen with oxygen.

Maintaininr, the concer.tiation of hydrogen or oxygen below their flammability limits 4

prov1 des assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Des 10n Criterion 60 of Appendix A to 10 CFR Part $0.

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/vnendment Nos. E6.735 1

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l 5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclu'; ion area is shewn oa figure 5.1-1.

LOW POPUL ATION 20NE s

5.1.2 The low population zone is shown on figure 5.1-2.

SITE BOUNDARY 5.1.3 The UNRESTRICTED AREA and SITE BOUNDARY for radioactive liquid effluents is shown on Figure 4.1-3.

The UNRESTRICTED AREA and SITE B0VHDARY for radio-active gaseous effluents is shown on figure 5.1-4.

5. 2 CONTAINMENT CONFIGURAT103 5.2.)

The containment structure is comprised of a steel containment vessel.

having the shape of a right circular cylinder with a hemispherical dome and ellipisodal bottom surrounded by a reinforced concrete shield building.

5._2.1.1 CONTAINMENT VESSEL a.

Nominal inside diameter = 130 feet, b.

Nominal inside height 285.5 feet, 0

c.

Net free volume = 2.834 x 10 cubic feet.

d.

Nominal thickness of vessel walls - 1 1/2 inches, e.

Nominal thickness of vessel dome - 13/16 inches.

f.

Nominal thickness of vessel bottom - 1 1/2 inches.

5. _2.1. 2 SHIELD BUILDlHG a.

Minimum annular space = 4.5 feet, b.

Annulus nominal volume = 678.700 cubic feet, c.

Nominal outside height (measured from top of foundation base to the top of the dome) = 279.5 feet.

d.

Nominal inside diameter = 139.25 feet, e.

Cylinder wall minimum thickness = 2.5 feet.

f.

Dome minimum thickness = 2.0 feet.

9 Dome inside radius = 125.29 feet.

4 DAVIS-BESSE, UNT' 1 5-1 Amendment No.170

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4 if. 4t4 I)h "_ H ( 4'd k uil 1 l l I i i a ~ E DAVI5 BESSE, UNIT _1 5'-10 ~ L Amendment"No. $p,170 l i. I y sy f3 p4.- ,71,--- -m-

AuilNISTRATIVE CONTROLS j 6.8.4 (Continued) c. Post-Accident Sampling i A program which will ensure the capability to obtain and analyse reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containm,ent atmosphere sampics 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. d. Radioactive Effluent Controls Progiam A program shall be provided conforming with 10 CTR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS Of THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements: 1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the-methodology in the ODCM. 2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRIC1ED AREAS conforming to 10 CFR Part 20. Appendix B. Table,II, Column 2, 3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology.and parameters in the ODCM, 6 4) Limitations on the annual and quarterly doses or dose comnit-ment to a MEMBER Of THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix ! to 10 CFR Part 50, 5) Determination of cumulative and projected dose contributions from radioactive e,ffluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, DAVIS-BESSE, UNIT 1 6-14a Amerdment No. J7,EA.PJ,170

L i ADMINISTRATIVE CONTROLS 6.8.4 (Continued) d. Radioactive Effluent Controls prog am (Continued) 6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radio-activity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix ! to 10 CFR Part 50, 7) Limitations on the dose rate resultino from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY confoming to the doses associated with 10 CFR Part 20 Appendix B. Table 11 Column 1, 8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix 1 to 10 CFR Part 50, 9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from lodine-131. lodine-133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY confoming to Appendix 1 to 10 CFR Part 50, 10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190. _e._ Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) repre-sentative measurements-of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. Theprogramshall(1)becontainedintheODCM,(2) conform to the guidance of Appendix ! to 10 CFR Part 50, and (3) include the following: 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance..ith the method-ology and parameters in the CDCM, 2) A Land Use-Census to ensure that changes-in the use of areas at and beyond the SITE BOUNDARY are identified and that modifica-tions to the monitoring progret are made if required by the results of this census, and DAVIS-BESSE - UNIT-1 6-14b Amendment No.170

s l ADMINISTRATIVE CONTROLS 6.8.4 (Continued) Radiological Environmental _ Monitoring Program (Continued) e. 3) Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are perfonned as part of the quality assurance program for environmental monitoring. 6.9 REPORTING REQUIREMENTS ROUTINE rep 0RTS 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 testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different desi manufactured by a different fuel supplier, and (4)gn or has b'een modifications that may have significantly altered the nuclear, thenna1, or hydraulic performance 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 operating conditions or characteristics obtained during the test program and 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 included in this report. 6.9.1.3 Startupreportsshallbesubmittedwithin(1)90daysfollowing completion of the startup test program, (2) 90 days following resumption or commencement of comercial 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 progrem, and resumption or comencement of comercial DAVIS-BESSE, UNIT 1 6-14c Amendment No. M,#,170 ~.

ADji!NISTRATIVE CONTROLS D CORE OPERATING Lif41TS REPORT (Continued) 8) DAW 10119, " Power Peaking Nuclear Reliability factors." June 1977 The methodology for Rod Program received NRC approval in the Safety Evaluation i dated January 11, 1990. The core operating limits shall be determined 50 that all applicable limits l (e.g. fuel thermal-mechanical limits, core thennal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident i analysis limits) of the safety analysis are met. The CORE OPERATING LIMITS REPORT, including any mid-cycle revision or supple. ments thereto, shall be provided upon issuance icr each reload cycle to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector. t i i t t l .l i. 3 DAVIS-BESSE, UNIT 1 6-17 Amendment No.144

r t ? ADMINISTRATIVE CONTROLS I - ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 5.9.1.10 The Annual Radiological Environmental Operating Report covering l the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries. l interpretations, and analysis of trends of the results of the Radiological l Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM, and (2) Sections IV.B.2. IV.B.3, and IV.C of Appendix ! to 10 CFR Part 50. SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REl9RT 6.9.1.11 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid and. ~ gaseous effluents and solid waste released from the unit. The material - provided shall be (1) consistent with the objectives outlined in the ODCM and PCP, and (2) in conformance with 10 CER 50.36a and Section IV.B.1 of Appendix 1 to 10 CFR Part 60. c l. DAVIS-BESSE, UNIT 1 6-17a Amendment No. Ef> 73,170 ) <v-e -w=r-vew ,w,,-wm.e- ,m .-ev-wm--n,_., ,, _, --.e e,y- --.g-9. ,.w ,-.-.,.w.., - _..., _.. _

I _A.DMINISTRATIVE CONTROLS $PECIAL REPORTS l 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory i Connission in accordance with 10 CFR 50.4 within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference 3 specifications: a. ECCS Actuation, Specifications 3.S.2 and 3.S.3. B. Inoperable Seismic Monitoring Instrumentation Specification 3.3.3.3. c. Inoperable Meteorological Monitoring Instrumentation Specification 3.3.3.4 d. Seismic event analysis, Specification 4.3.3.3.2. e. Fire Detection Instrumentation, Specification 3.3.3.8. f. Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2. 6.10 RECORD RETENTION l 6.10.1 The following records shall be retained for at least five years: a. Records and logs of facility operation covering time interval 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 EVENTS. d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications, e. Records of changes made to Operating Procedures. f. Records of radioactive shipments. 9 Records of sealed source and fission detector leak tests and results. h. Records of annual physical inventory of all sealed source material of record. P DAVIS-BESSE,' UNIT 1 6-18 Amendment No._p,J2,55,EE,Jp5,J35,170

4 ADMINISTRAT!VE CONT _ROLS 6.10.2 The following records shall be retained for the duration of the facility Operating License: a. Records and drawing changes reflecting facility design modifica-tions made to systems and equipment described in the Final Safety Analysis Report, b. Reerds of new and irradiated fuel inventory, fuel transfers and assembly burnup histories. c. Records of radiation exposure for all individuals entering radiation control areas. -d. Records of gaseous and liquid radioactive material released to the

environs, e.

Records of transient of operational cycles for those facility components identified in Table 5.71. f. Records of reactor tests and experiments, g. Records of training and qualification for current members of the plant staff. h. Records of in-service inspections performed pursitant to these Technical Specifications, i. Records of Quality Assurance activities required by the QA Manual, j. Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59. k. Records of meetings of the SRB and the CNRB. 1. Records for Environmental Qualification which are covered under the provisions of paragraph 6.13. m. Records of analyses required by the radiological environmental monitoring program that would permit evaluation of the accuracy of the analyses at a later date. This should include procedures effective at specified times and QA records showing that these l procedures were followed. o. Records of the service lives of all safety related hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records. -p. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM. DAVIS-BESSE, UNIT 1 6-19 Amendment No. E.72 ES.7/.170

ADMINISTRATIVE CONTR_0L 6.13 ENVIRONMENTAL QUAllflCAT10_N 6.13.1 By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors"(DORguide'iines) or, NUREG-0588 " Interim Staff Position on Environmental Qualification of Safety Related Electrical Equipment". December 1979. Copies of these documents are attached to Order for Modi-fication of License NPF-3 dated October 24, 1980. 6.13.2 By no later than December 1,1980, complete and auditible records must be available and maintained at a certain location which describe the environmental qualification method used for all safety related electrical equipment in sufficient detail to document the degree of compliance with the DDR Guidelines or liUREG-0588. Thereaf ter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified. DAVIS-BESSE, UNIT 1 6-21 Order dated October 24, 1980

l l . ADMINISTRATIVE _ CONTR0_LS 6.14 PROCESS CONTROL PROGRAM (PCP) ) Changes to the PCP: j a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.p. This documentation shall j contain: 1) Sufficient information to support the change together with the appropriate aralyses or evaluations justifying the change (s), and 2) A determination that the change will maintain the overall confomance of the solidified waste product to existing require-ments of Federal State, or other applicable regulations. b. Shall become effective after review and acceptance by the SRB and the approval of the Plant Manager. 6.15 0F FSITE DOSE CALCUL A110N MANUAL _ (0DCM1 Changes to the ODCM: a. b il1.e documented and records of reviews performed shall be retained as re' uired by Specification 6.10.2.p. This documentation shall contain: 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190.10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations. b. Shall become effective after review and acceptance by the SRB and the approval of the Plant Manager. c. Shall be submitted to the Comission in t'he form of a complete, legible copy of the entire ODCM as part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearlyindicating(e.g.areaofthepagethatwaschanged,andshall the indicate the date , month / year) the change was implemented. l DAVIS-BESSE, UNIT 1 6-22 Amendment No. U,170 i -}}