Text

Amend 86 to License NPF-3,revising Tech Specs Re Radioactive Effluent Mgt,Including Monitoring,Reporting & Environ Surveillance
	ML20129J696
Person / Time
Site:	Davis Besse
Issue date:	07/02/1985
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Toledo Edison Co, Cleveland Electric Illuminating Co
Shared Package
ML20129J698	List: ML20129J696; ML20129J705;
References
	NPF-03-A-086 NUDOCS 8507230248
	Download: ML20129J696 (100)
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UNITED STATES 8

NUCLEAR REGULATORY COMMISSION o

h WASHINGTON, D. C. 20555 y*****)

TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No. NPF-3 1.

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

A.

The application for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated March 16, 1979, as supplemented by letters dated December 23, 1982, July 13, 1983 August 18, 1983, March 15, 1984, and November 1, 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 Comission'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:

8507230248 850702 PDR ADOCK 05000346:

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1 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 86, are hereby incorporated in the license. The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

- 3.

This license amendment becomes effective on October 30, 1985.

FOR THE NUCLEAR REGULATORY COMMISSION

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. Stolz, Chief

/0 rating Reactors Branch f4

' ivision of Licensing Attach 6ent:

Changes to the Technical Specifications Date of Issuance: July 2,1985 O

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ATTACHMENT TO LICENSE AMENDMENT NO.85 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace or add the following pages of the Appendices "A" and "B" Technical Specifications with the enclosed 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 completeness.

Appendix A Paces Appendix B Paoes I

3/4 11-18 6-22 i

Ia 3/4 11-19 6-23 iii

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IV 3/4 11-20 6-24 iv VIIIa 3/4 12-1 2.1-1 XIII 3/4 12-2 2.1-2 through 1-6a 3/4 12-3 2.1-18(Delete) 1-6b 3/4 12-4 3.2-1 1-8 3/4 12-5 3.2-2 through 3/4 3-57 3/4 12-6 3.2-11 (Delete) 3/4 3-58 3/4 12-7 5.4-1 3/4 3-59 3/4 12-8 5.4-2 3/4 3-60 3/4 12-9 5.4-3 3/4 3-61 3/4 12-10 5.4-4 3/4 3-62 3/4 12-11 5.5-1 3/4 3-63 3/4 12-12 3/4 3-64 3/4 12-13 3/4 3-65 B 3/4 3-6 3/4 3-66 B 3/4 11-1 3/4 3-67 B 3/4 11-2 3/4 11-1 B 3/4 11-3 3/4 11-2 B 3/4 11-4 3/4 11-3 B 3/4 11-5

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3/4 11-4 B 3/4 11-6 3/4 11-5 B 3/4 11-7 3/4 11-6 B 3/4 12-1 3/4 11-7 6-7 3/4 11-8 6-8 3/4 11-9 6-11 3/4 11-10 6-12 3/4 11-11 6-13 3/4 11-12 6-17a 3/4 11-13 6-17b 3/4 11-14 6-17c 3/4 11-15 6-18 3/4 11-16 6-18a 3/4 11-17 6-19a

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t INDEX s

DEFINITIONS SECTION PAGE t

1.0 DEFINITIONS 1

1 D E F I N E D T E RMS......................'........................

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

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

1 OPERATIONAL M0DE........................................'..

1-1 ACTI0N.....................................................

1,-1 OP E RA B L E - OP E RA B I L I TY....................................

1-1 R EP O RTAB L E OCCURREN CE.....................................

1-2 CONTAINMENT NTEGRITY......................................

1-2 I

CHANNEL CALIBRATION........................................

1-2

' CHANNEL CHECK...........................................

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

1-3 CORE ALTEnATI0N............................................

1-3

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

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

1-3 U N I DE NTI F I ED L EA KAG E........................................

1-4 PRESSURE B0UNDARY LEAKAGE..................................

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

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

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

1-4 E-AVERAGE DISINTEGRATION ENERGY............................

1-4

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STAGGERED TEST BASIS.......................................

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

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

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

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

1-5 SAF ETY FEATURE RESPONSE TIME...............................

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

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

1-6 SOURCE CHECK...............................................

4 -6a

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PROCES'S CONTROL PR0 GRAM....................................

1-6a I' David-uddSE UNIT i 1

Amendment No.,;Mr 86 e

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INDEX s

DEFINITIONS SECTION PAGE 1.0 DEFINITIONS (Continued)

SO L I D I FI CAT I ON........................................

1-6a OFFSITE DOSE CALCULATION ltANUAL (ODCt1)................

1-6a GASEOUS RADWASTE TREATMENT SYSTEM.....................

1-6a VENTILATION EXHAUST TREATiiENT SYSTEM..................

1-6a PURG,E-PURGING.........................................

1-Gb v E NT I n G...............................................

1-6b MEMB E R ( S ) 0 F TH E PU8 L I C...............................

1-6b 5ITE 80VNDARY.........................................

1-6b UNRESTRICTED AREA.....................................

1-6b DEWATERING............................................

1-6b OPERATIO.'IAL MODES (TABLE 1.1 ).........................

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

1-8 r

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DAVIS-BESSE, UNIT 1 Ia Amendment No. 86 e

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l INDEX I

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS l

SECTION PAGE l

2.1 SAFETY LIMITS l

R e a c to r Co r e..............................................

2-1 l

Rea ctor Coolant Sys tem Pressure...........................

2-1 i

l l

2.2 LIMITING SAFETY SYSTEM SETTINGS l

Reactor Protection System Setpoints......................

2-4 l

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8ASES SECTION PAGE 2.1 SAFETY LIMITS R ea c tor Co r e...................................... ;....... 8 2-1

~~feactorCoolantSystemPressure...........................

8 2-3 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Protection System Instrumentation 5etpoints.......

8 2-4 l

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DAVIS-BESSE, UNIT 1 II Amendment No. 38 l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS -

SECTION PAGE 3/4.0 APPLICABILITY'..........................................

3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 80RATIONCONTRbL

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Shu tdown Ma rg i n...................................... 3/4 1-1 Ba ron O i l ut i on.............'.........................

3/4 1-3 Modera tor Temperature Coef fi cient.................... 3/41-4 Minimum Temperature for Criticality..................

3/4 1-5 3/4.1.2 BORATION SYSTEMS Fl ow Pa ths - 5hutdown................................ 3/4 1-6

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Fl ow Paths - Opera ting...............................

3/4 1-7 Makeup Pump - 5hutdown............................'..'.

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

3/4 1-10 Decay Heat Removal Pump - Shu tdown................... 3/4 1-11 Boric Acid Pump - Shutdown...........................

3/4 1-12' loric Acid Pumps - Operating.........................

3/4 1-13 Scrated Wa ter Sources - Shutdown.....................

3/4 1-14 Bora ted Wa ter Sources - Opera ti ng....................

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

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

3/4 1,-21 I

Posi ti on Indica tor Channel s..............,............ 3/4'l-22 Rod Drop Time........................................

3/4 1-24 Safety Rod Insertion Limit...........................-

3/4 1-25 Regulating And Insertion Limits......................

3/4 1-26 And Program..........................................

3/4 1-30 tenon, Reactivity.....................................

3/4 1-33

, Axial Power shaping And Insertion Limits.............'.'

3/4 1-34 l

DAV!5-8E55E. 18817 1 III Amendment No. 38

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIRDfENTS SECTION pAgg 3-3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXI AL POWER IMBALANCE................................ 3/4 2-1 3/4.2.2 NUCLEAR HEAT FLUX HOT-CHANNEL FACTOR - F................................

3/42-5 n

' 3/4.2.3 NUCLEAR ENTHALPY RISE N

HOT CHANNEL FACTOR - FAH...........................

3/42-7 3/4.2.4 QUADRANT POWER TILT................'..................

3/42-9 3/4.2.5 DNB PARAMETERS.......................................

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 SYSTDis INSTRUMEhTATION

-Sa fety Features Actua tion Sys tem..................... 3/4 3-9 S team and Feed Rupture Control Sys tem................ 3/4 3-23 Anti cipa tory Reactor Trip Sys tem...................

3/4 3-30a 3/4. 3.3 MONITORING INSTRUMENTAT.CN Ra di a tien Moni tori ng Ins :rr.er.:a ti on................. 3/4 3-31 Incore Detectors.....................................

3/4 3-35 Seismic Instrumentation..............................

3/4 3-37 Meteorol ogi cal Instrumenta ti on...... '..............'... 3/4 3-40

. Remote Shutdown Ins trumenta tion...................... ' 3/4 3-43 Post-Accident Instrumentation...................'.....

3/4 3-46

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Chl o ri ne Detecti on 5ys t ens......................'...... 3/4 3-51 Fi re Dete cti on Ins trunentati on.............'...........

3/4 3-52 Radioactive Liquid Effluent Monitoring Instrumentation 3/4 3-57 3/4.4 REACTOR CDOLANT SYSTEM 3/4.4.1 CD0LANT LOOPS AND COOLANT CIRCULATION Sta rtup an d Powe r 0pera ti on........................... 3/4 4-1 Shutdown and Hot Standby..

3/4 4-2 3/4.4.2 SAFETY VALV ES - 5HUTDOWN.............................. 3/4 4-3 3/4.4.3 5AFETY VALVES AND ELECTROMATIC RELIEF YALVE - OPERATING 3/4 4-4 DAVIS-BESSE, UNIT 1 IV Amendment No. 78. 86

O INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LI QUI D E FFL UENTS.............................. 3/4 11-1 Co n c e n t ra t i o n.................................

3/4 11-1 Dose..........................................

3/4 11-5 Liquid Radwaste Treatment System..............

3/4 11-7 Li qui d Hol dup Ta n ks...........................

3/4 11-8 3/4.11.2 MS EOUS E FFLUENTS.............................

3/4 11-9 Dose.........................................

3/4 11-9 Do s e - No bl e Ca s es....'........................

3/4 11-13 Dose - Iodine-131, Tritium, and Radionuclides I n Pa r t i c u l a t e Fo rm........................

3/4 11-14 Gas eous Radwas te Trea tment Sys tem............. 3/4 11-16 Ex pl os i ve Ga s Mi x tura.........................

3/4 11-17 3/4 11.3 SOLID RADI0 ACTIVE WASTE.......................

3/4 11-18 3/4 11.4 TOTAL 00SE....................................

3/4 11-20 3/4.12 RADIOLOGICAL ENVIRONMENTAL HONITORING 3/4.12.1 MONITORING PR0 GRAM............................

3/4 12-1 I

3/4:12.2 LAN D US E C EN S US...............................

3/4 12-12 3/4.12.3 INTERLABORATORY C0f1 PARIS 0N PROGRAM............

3/4 12-13 l

DAVIS-SESSE, UNIT 1 VIIIa Amendment No. 86 l

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ll INDEX BASES

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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 CIRCULAT10N................................

B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM.....

B 3/4 9-2 l

3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND l

STORAGE POOL WATER LEVEL...........................

B 3/4 9-2 3/4.9.12 STORAGE POOL VENTILATION...........................

B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP. HEIGHT, INSERTION AND r

POWER DISTRIBUTION LIMITS........................

B 3/4 10-1 1

3/4.10.2 PHYSICS TESTS......................................

B 3/410-1 l

3/4.10.3 REACTOR COOLANT L00PS..............................

B 3/4 10-1 l

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3/4.10.4 SHUTDOWN MARGIN....................................

B 3/410-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 L I QU I D E F FLU E NTS................................... B 3/411-1 3/4.11.2 G ASEOUS E F FLUENTS.................................. B 3/4 11-3

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3/4.11.3 S O L I D RA DI 0A CT I V E WASTE............................ B 3/411-6 3/4.11.4 TOTA L D0 S E......................................... B 3/411-7 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM.................................

B 3/412-1 3/4.12.2 LAND USE CENSUS....................................

B 3/412-1 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM.................

B 3/412-1 r

DAVIS-EESSE, UNIT 1 XIII Amendment No. 85

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Ex c l u s i o n A rea............................................

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

5-1 5.2 CONTAINMENT Configuration.............................................

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

5-4 5.3 REACTOR CORE Fu el As s en b11 e s...........................................

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

5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature...........................

5-4 l

Volume....................................................

5-5 5.5 METEORLOGICAL TOWER LOCATION..............................

5-5' 5.6 FUEL STORAGE Criticality...............................................

5-5

- -- D r a i n a g e..................................................

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

5-6 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT.......................

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

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DEFINITIONS

_s SOURCE CHECK 1.29 A SOURCE CHECK shall be the observation of channel upscale response when the channel sensor is exposed to a radioactive source.

PROCESS CONTROL PROGRAM 1.30 A PROCESS CONTROL PROGRAM (PCP) shall provide details for the sampling, analysis, and evaluation from which SOLIDIFICATION or DEWATERING radioactive wastes from liquid systems is assurea.

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SOLIDIFICATION 1.31 SOLIDIFICATION shall be the conversion of wet radioactive wastes into a form that meets destination waste disposal site criteria by removal of freestanding water through chemical processes.

OFFSITE DOSE CALCULATION MANUAL (00CM) 1.32 The OFFSITE DOSE CALCULATION MANUAL (00CM) shall be a manual containing the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints. Requirements of the 00CM are provided in Specification 6.14.

GASEOUS RADWASTE TREATMENT SYSTEM

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1.33 The GASEOUS RADWASTE TREATMENT SYSTEM is a system that is designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases and providing for decay for the purpose of reducing the total radioactivity prior to release to the environment.

VENTILATION EXHAUST TREATMENT SYSTEM 1.34 A VENTILATION EXHAUST TREATMENT SYSTEM is a system that is designed and installed to reduce radioactive material in particulate form in affluents by passing ventilation or vent exhaust gases through HEPA filters for the purpose of removing particulates from the gaseous exhaust stream prior to the release to the environment. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

DAVIS-8 ESSE, UNIT 1 1-Ga Amendment flo. 86 n-

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DEFINITIONS PURGE-PURGING 1.35 PURGE OR PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, con-centration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

VENTING 1.36 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required ~during VENTING. Vent, used in system names, does not imply a VENTING process.

MEMBER (S) 0F THE PUBLIC 1.37-MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally 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 recreational, 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.

l 1

i UNRESTRICTED 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 within 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 UN-RESTRICTED AREA boundary may coincide with the exclusion (fenced) area bnund-ary, as defined in 10 CFR 100.3(a), but the UNRESTRICTED AREA does not i.J lude areas over water bodies. The concept of UNRESTRICTED AREAS, established at or beyond the SITE BOUNDARY, is utilized in the LIMITING CONDITIONS FOR OPERATION l

to keep levels of radioactive materials in liquid and gaseous affluents as low l

at is reasonably achievable, pursuant to 10 CFR 50.36a.

OEWATERING 1.40 DEWATERING is the conversion of wet radioactive wastes into a form that meets destination waste disposal site criteria by removal of freestanding water through physical processes.

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OAVIS-BESSE, UNIT 1 l-6b Amendment No. 86

t

.4 TABLE 1.1 OPERATIONAL MODES REACTIVITY

% RATED AVERAGE COOLANT MODE CONDITION, K,ff THERMAL POWER

TEMPERATURE

.l.

POWER OPERATION

> 0.99

> 5%

> 280*F 2.

STARTUP 1 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 5.

COLD SHUTDOWN

< 0.99 0

< 200*F 6.

REFUELING **

< 0.95 0

< 140*F

' Excluding de:ay heat.

Reactor vessel head uncolted or removed anc fuel in the vessel.

W

a DAVIS-BESSE, UNIT 1 1.f

TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

W At least once per 7 days.

N At least once per 31 days.

Q At least once per 92 days.

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SA At least once per 6 months.*

R At least once per 18 months.*

S/U Prior to each reactor startup.

P Prior to each release.

N/A Not applicable.

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

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l DAVIS-BESSE, UNIT 1 1-8 Amendment No. 37, 86 l

INSTRUMENTATION gs RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION O

LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-15 shall be OPERA 8LE with their alare/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 a-o not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULA-TION MANUAL (00CM).

APPLICA8ILITY: At all times.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-15.

Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not appitcable.

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SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERA 8LE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION AND CHAhNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-15.

DAVIS-BESSE, UNIT 1 3/4 3-57 Amendment No. 85 l

1 TA8LE 3.3-15 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION asC NINIMtM NI CHANNELS INSTRUMENT OPERA 8LE APPLICABILITY ACTION U

1.

Gross Radioactivity Monitors e

Providing Alarms and Automatic Termination of Release a.

Liquid Radwaste Effluent Line 1

(1) 18 (either Miscellaneous or Clean, but not both simultaneously)

M 2.

Flow Rate Measurement Devices a.

Liquid Radwaste Effluent Line 1

(1) 19 b.

Dilution Flow to Collection Box 1

(1) 19 3.

Gross Beta or Gamma Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release g

a.

Turbine Building / Storm Sewer Drain 1

(1) 19, 20 E

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eli TABLE 3.3-15 (Continued)

TABLE NOTATION g

(1) During radioactive releases via this pathway 3

ACTION 18 With the number of channels OPERA 8LE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be resumed, provided that prior to initiating a release:

1.

At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1 for analyses performed with each batch;

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2.

At least two independent verifications of the release rate calculations are performed; 3.

At least two independent verifications of the discharge valving are performed; Othenvise, suspend release of radioactive effluents via this pathway.

ACTION 19 With the number of channels OPERABLE less than required by the Minimum Channels OPERA 8LE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves may be used to estimate flow.

ACTION 20 With the number of channels OPERA 8LE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a lower limit of detection no great-er than,,,.10-7 ci/m1.

p DAVIS-8 ESSE, UNIT 1 3/4 3-59 A::lendment No. 86

I i TABLE 4.3-15 k

RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Y

3 CHAMEL M

CHAMEL SOURCE CHANNEL FUNCTIONAL INSTRtMENT CHECK CHECK CAllBRATION TEST Ey 1.

Gross Beta or Gamma Radioactivity Monitors Providing Alarm and g

Automatic Isolation III I3)

Q(2) a.

Liquid Radwaste Effluents Line D

P R

2.

Flow Rate Monitors I4) a.

Liquid Radwasta Effluent Line D

N.A.

R Q

M I4I b.

Dilution Flow to Collection Box D

N.A.

R Q

Y8 C

c

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TA8LE 4.3-15.(Continued)

TABLE NOTATION (1) During releases via this pathway.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the alarm / trip setpoint.

(3) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NSS. These standards should permit calibrating the system over its intended range of energy and rate capabilities.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per eighteen months. For high range monitoring instrumentation, where calibration with a radioactive source is impractical, an electronic calibration may be substituted for the radiation source calibration.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made, s

DAVIS-BESSE, UNIT 1 3/4 3-61 Amendment flo. 86

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i INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4

LIMITING CONDITION FOR OPERATION e

1 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels i

shown in Table 3.3-16 shall be OPERA 8LE with their alare/ trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in acct? dance with the methodology and parameters in the 00CM.

APPLICA8ILITY: As shown in Table 3.3-16.

~

ACTION:

a.

With a radioactive gaseous affluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, without delay suspend the release of

)

radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative, b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERA 8LE, take the ACTION shown in Table 3.3-16.

Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS

~.-

l 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel I

shall be demonstrated OPERA 8LE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-16.

~

DAVIS-BESSE, UNIT 1 3/4 3-62 Amendment No. 86 m.

o. -., o 1

TABLE 3.3-16 i

E j

RADIDACTIVE' GASEOUS EFFLUENT MONITORING INSTRUMENTATION Y

em 3

MINIMUM

.m CHANNELS INSTRUMENT OPERABLE APPLICA8ILITY PARAMETER ACTION U

1.

Wasta Gas Decay System (provides automatic isolation)

H a.

Noble Gas Activity Monitor 1

(1)

Radioactivity Measurement 25 b.

Effluent Systes Flow Rate 1

(1)

System Flow Rate Measurement 26 g

Measuring Device

=

w 2.

Waste Gas System g

(provides alare function) a.

Oxygen Monitor 1

(2)

% 0xygen 28 3.

Containment Purge Monitoring Systes (provides automatic isolation)-

a.

Noble Gas Activity Monitor 1

(1)

Radioactivity Measurement 27 N

a 3n

1 TABLE 3.3-16 (Continued) i k

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRtMENTATION U

6 O

MINIMLM M

CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION Ey 4.

Station Vent Stack e

(provides alarm function) a.

Noble Gas Activity Monitor 1

(1)

Radioactivity Measurement 27 b.

Iodine Sampler Cartridge 1

(1)

Verify Presence of 29 Cartridge c.

Particulate Sampler Filter 1

(1)

Verify Presence of 29 w)

F11ter d.

Effluent System Flow 1

(1)

System Flow Rate 26 E

Rate Measuring Device Measurement e.

Sampler Flow Rate Measuring.

1 (1)

Sampler Flow Rate 26 Device Measurement Y

a*

.O f

0

)

i 1'

\\

8' TA8LE 3.3-16 (Continued)

TA8LE NOTATION i.

(1) During radioactive waste gas releases via this pathway.

(2) During additions to the waste gas surge tank ACTION 25 With the number of channels OPERA 8LE less than required by the Minimum Channels OPERA 8LE requirement, the contents of the tank may be re' eased to the environment provided that prior to initiating the release:

1.

At least two independent samples are analyzed in accordance with Specification 4. 11.2.1.1 for analyses

~

performed with each batch; 2.

At least two independent verifications of the release rate calculations are performed; 3.

At least two independent verifications of the dis-charge valving are performed.

ACTION 26 With the number of channels OPERA 8LE less than required by the Minimum Channels OPERA 8LE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 27 With the number of channels OPERABLE less than required by the Minimus Channels OPERA 8LE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I

~

ACTION 28 With the number of channels OPERABLE less than required by the Minimum Channels OPERA 8LE requirement, additions to the waste gas surge tank may continue provided another method for ascert-aining oxygen concentrations, such as grab sample analysis, is implemented to provide measurements at least once per four i

(4) hours during degassing and daily during other operations.

ACTION 29 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously I

collected with auxiliary sampling equipment, as required in Table 4.11-2.

i l

DAVIS-8 ESSE, UNIT 1 3/4 3-65 Amendment No. 86 I

^

t TABLE 4.3-16 O

.D RADIDACTIVEGASEOUSEFFLUINTMONITORINGINSTRtMNTATIONSURVEILLANCEREQUIREENTS

'?

==0 CNAWlEL E

CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRtN NT CHECK _

CHECK CALIBRATION TEST M

1.

Waste Gas Decay System a.

Noble Gas Activity Monitor P

P R(5) q(3)

III III N/A R

q b.

Effluent System Flow Rate P

M 2.

Waste Gas System a.

Oxygen Monitor D(2)

N/A Q(6)

N/A 3.

Containment Purge Vent System a.

Noble Gas Activity Monitor D

PIII;M(8) g(5) q(3)

III 4.

Station Vent Stack a.

Noble Gas Activity Monitor D

M R(5) q(4)

II)

I)

N/A N/A N/A b.

Iodine Sampler W

II) c.

Particulate Sampler W

N/A N/A N/A a

d.

System Effluent Flow Rate III 5

Measurement Device D

N/A R

N/A 2

e.

Sampler Flow Rate gg)

Measurement Device W

N/A R

N/A o,

1 TABLE 4.3-16 (Continued)

TABLE NOTATION l

i t

(1) During radioactive waste gas releases via this pathway.

(2) During additions to the waste gas surge tank.

(3) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the alarm / trip setpoint.

(4) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if the instrument indicates measured levels above the alare/ trip setpoint.

(5) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the

- reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities 1

with M85. These standards should permit calibrating the system over its intended range of energy and rate capabilities.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least'once per eighteen months. For high range' monitoring instrumen-tation, where calibration with a radioactive source is imprac-tical, an electronic calibration may be substituted for the radiation source calibration.

(6) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1.

One volume percent oxygen, balance nitrogen; and i

2.

Four volume percent oxygen, balance nitrogen.

(7) During containment purges.

(8) When used in a continuous mode.

)

s DAVIS-BESSE, UNIT 1 3/4 3-67 Amendment No. 86

r.,-

+;.

3/4.11 RADIOACTIVE EFFLUENTS O'

3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 3.11-1) shall be limited to the concentrations specified in 10 CFR Part 20.106 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microcuries/ml.

APPLICABILITY: At all times.

ACTION:

a.

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, without delay restore the concentration to within the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the 00CM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.

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

TABLE 4.11-1 1

RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSI5 PROGRAM Minimum Lower Limit j

Liquid Release Type Sampling Analysis Type of Activity of Detection Frequency Frequency Analysis (LLD) (pCi/ml)"

i P

P 7b A.

Batch Waste Each Batch Each Batch Principal Gamma 5 x 10 d

Release Tanks Emitters #

I-131 1 x 10'*

One Batch /M M

Dissolved and 1 x 10

~

Entrained Gases P

M H-3 1 x 10"*

C Each Batch Composite Gross Alpha 1 x 10'#

c Sr-89, Sr-90 5 x 10.s Eac Batch C

osite Fe-55 1 x 10"*

8.

Turbine Building Principal Gasuna 5 x 10 ' b l

Sump / Storm Continuous S,

Emitters #

Sewer Drain I

~

I-131 1 x 10 P

P 7b C.

Condensate Each Batch Each Batch Principal Gamma 5 x 10 I

Domineralizer Emitters Backwash f

1-131 1 x 10 l

l l

l DAVIS-BESSE, UNIT 1 3/4 11-2 Amendment No.86 l

l

k 5

TA8LE 4.11-1 (Continued) i f**

TABLE NOTATION a.

The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radio-chemical separation):

4.66 s g,

b E

V 2.22 Y

exp(-Aat) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume);

s is the standard deviation of the background counting rate or b of the counting rate of a blank sample as appropriate (as counts per minute);

E is the counting efficiency (as counts per transformation);

V is the sample size (in units of mass or volume);

2.22 is the number of transformations per minute per picocurie; Y is the fractional radiochemical yield (when applicable);

A is the radioactive decay constant for the particular radionuclide;

~

At for plant affluents is the elapsed time between the midpoint of sample collection and time of counting.

It should be recognized that the LLO is defined as an a priori (before the fact) limit representing 2e capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

s DAVIS-BESSE, UNIT 1 3/4 11-3 Amendment No. 85

TABLE 4.11-1 (Continued)

TABLE NOTATION b.

The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, and Ce-141. For Ce-144, the LLD is 2.0x10-s pCi/ml. Other peaks which are measured and identified shall also be reported.

Nuclides which are below the LLD for the analysis should not be reported as being present at the LLD level. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Semi-annual Radioactive Effluent Release Report.

~

c.

A composite sample is one in which the method of sampling employed results is a specimen which is representative of the liquids released.

d.

- A batch release is the discharge of liquid wastes of a discrete volume.

e.

When the monitor is out of service, a grab sample shall be taken and analyzed once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if the condensate pump discharge exceeds 1x10-s pCi/ml gross beta or gamma.

f.

If an isotopic anal'ysis is' unavailable, gross beta or gamma measurement of batch release may be substituted provided the concentration released to the unrestricted area does r.ot exceed 1 x 10-7 pCi/a1 and a composite sample is analyzed for principal gamma emitters when instrumentation is available.

i s

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

A RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radio-active materials in liquid effluents released to UNRESTRICTED AREAS (see Figure 3.11-1) shall be Ifmited:

a.

During any calendar quarter to less than or equal to 1.5 areas to the total body and to less than or equal to 5 areas to any organ, and b.

During any calendar year to less than or equal to 3 areas to

~

the total body and to less than or equal to 10 means to any organ.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current rJ1endar quarter and the current calendar year shall be determined in x:cordance with the methodology and parameters in the 00CM at least once per 31 days.

DAVIS-BESSE, UNIT 1 3/4 11-5 Amendment No. 86

E;:

5 0

5 5

y<b oW

o. < w ES I

$O B5 WE3" "a

i

- g W W !i:-

Z r

I um-

=g

.r t.

,. ~ 5 'h.1'i hg

,; i -/.

I

.i j

i i:

1 j{

'l

'.d 4i i

i j

. 4 j

7 j

,i 4

4 4

J

,j i

i 4

I

4

,i. q's'. g! i

~

q q

3:-

i d i 4

=

j i

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I,a 3-- r; 4

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jih T- )

4 4

i9 n

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.f j j Ih J

j

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4 T

i i 'n i I v.

i

. ik E

i E

DAVIS-BESSE, UNIT 1 3/4 11-6 Amendment No. 86

i

4 i

RA010 ACTIVE EFFLUENTS

~

LIQUID RA0 WASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION I

3.11.1.3 The liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid affluent to UNRESTRICTED AREAS (see Figure 3.11-1) would exceed 0.06 area to the total body or 0.2 area to any organ in a 31 day period.

APPLICA8ILITY: At all times.

ACTION:

a.

With radioai:tive liquid waste being discharged without treatment and in excess of.the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, i

pursuant to Specification 6.9.2,a Special Report that includes the following information:

1 1.

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

j 2.

Action (s) taken to restore the inoperable equipment to OPERA 8LE status, and 3.

Sunnary description of action (s) taken to prevent a recurrence.

(

b.

The provisions of specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 1

4.11.1.3 In any month in which radioactive liquid effluent is being discharged without treatment, doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the 00CM.

DAVIS-BESSE, UNIT 1 3/4 11-7 Amendment No. 86

,,,~------------,,r-mm-

~~e-~-

,-~. - ~ -

RA010 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS

LIMITING CON 0! TION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

a.

Outside temporary tank.

APPLICABILITY: At all times.

ACTION:

a.

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

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material containeJ in each of the above listed tanks shall be determined to be within the above 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.

l

" Tanks included in this specification are those outdoor tanks that are 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 to the liquid radweste treatment system.

l l

l I

DAVI$-SESSE, UNIT 1 3/4 11-8 Amendment No.86

b.

g A

$.(

RADICACTIVE EFFLUENTS 3/4.11.2 GASE0US EFFLUENTS DOSE RATE i

LIMITING CON 0! TION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the 51TE BOUNDARY (see Figure 3.11-2) shall be limited to the following:

a.

For noble gases: Less than or equal to 500 acess/ year to the total body and less than or equal to 3000 aress/ year to the skin, and

~

b.

For iodine-131, for tritius, and for all radionuclides in particulate form with half lives greater than 8 days:

Less than or equal to 1500 mroes/yr to any organ.

APPLICA81LITY: At all times.

ACTION:

a.

With the dose RATE (s) exceeding the above Ifmits, without delay restore the release rate to within the above limit (s).

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEf t t,ANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the eethodology and parameters in the 00CM.

4.11.2.1.2 The dose rate due to iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the 00CM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

l DAVIS IESSE, UNIT 1 3/4 11-9 Amendment No. 85

l TASTE 4.11-2 BASI 0 ACTIVE GASE0ttS WASTE SApetIIIG AIEB AllALYSIS PROGRAM E

Ninimum Leuer Lielt of y

Gaseems Release Type Sampling Analysis Type of Detection (gLB) g Frequency Frequency Activity Analysis (pCl/el)

E P

P Waste Gas Becay Each Each Principal Gamma Emitters" 1 x le'.

~

Belease Release

-4 Grah Sample N-3 1 x le e

P P

c Centalament Purge Each Purge Each Purge Principal Gamma Emitters 1 x le Grah Sample W3 1 x 10 m

N N

Principal Gamme Emitters" 1 x 10"*

y Station vent Stack Grab Sample W3 1 x 10 g

U h

as Continuous Charcoal I-131 1 x 10 Sample Partifulate Principal Gamma Ealtters*

1 x 10'"

h Continuous Sa.,ie N

N h

Continuous g,,,,,gg*

~'

g Gross Alpha 1 x 10 a

Particulate Sample E

0 b

Continuous Composite

~'

Sr-89, Sr-90 1 x 10 g

Particulate Sample b

Continuous Mle hs M le hses a

Monitor Gross Beta or Gamma 1 x 10

s TABLE 4.11-2 (Continued)

TA8LE NOTATION a.

The LLD is the senilest concentration of radioactive material in a sample that will be detected with 955 probability with 55 probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radio-chemical separation): -

g, 4.66 sb E

V 2.22 + Y exp(-Aat) l where l

LLD is the lower limit of detection as defined above (as pCi per unit mass or volume);

s is the standard deviation of the background counting rate or b

i of the counting rate of a blank sample as appropriate (as counts per minute);

E is the counting efficiency (as counts per transformation);

V is the sample size (in units ef mass or volume);

2.22 is the number of transformations per minuta per picoeurie; Y is the fractional radiochemical yield (when applicable);

A is the radioactive decay constant for the particular radionuclide; At for plant effluents is the elapsed time between the sidpoint of sample collection and time of counting.

t It should be recognized that the LLD is defined as an 1 priori f

(before the fact) limit representing the capability of a measurement I

system and not as a posteriori (after the fact) Itait for a t

particular measurement.

b.

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1 and 3.11.2.3.

DAVIS-SESSE, UNIT 1 3/4 11-11 Amendment No. 86

TABLE 4.11-2 (Continued)

TABLE NOTATION The principal gamma emitters for which the LLD specification will apply c.

are exclusively the following radionuclides:

Kr-87. Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous euf ssions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137 Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measured and identified, together with the above nuclides, shall also be identified and reported.

Nuclides which are below the LLD for the analyses should be reported as "less than" the nuclide's LLD and should not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations. When unusual circumstances result in LLD's higher tnan required, the reasons shall be documented in the Semiannual Radioactive Effluent Release Report.

s DAVIS-BESSE, UNIT 1 3/4 11-12 Amendment No. 86

.' l RADI0 ACTIVE EFFLUEN'S T

[

DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY (see Figure 3.11-2) shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and b.

During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepara and submit to the Commiission within 30 days, l

pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective i

actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

~

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and

.~'

current calendar year for noble gases shall be determined in accordance with l

the methodology and parameters in the 00CM at least once per 31 days.

I I

l DAVIS-BESSE, UNIT 1 3/4 11-13 Amendment No. 86

?

RADIOACTIVE EFFLUENTS DOSE - IODINE-131. TRITIUM. AND RADIONUCLIOES IN PARTICULATE FORM LIMITINGCONDITIONFOROPERATIOk' 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous affluents released to areas at and beyond the SITE BOUNDARY (see Figure 3.11-2) shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 7.5 mress to any organ and, b.

During any calendar year:

Less than or equal to 15 arems to any j

organ.

APPLIJABILITY: Atdlltimes.

ACTION:

a.

With 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 any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that sub-sequent releases will be in compliance with the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

~

4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

s DAVIS-BESSE, UNIT 1 3/4 11-14 Amendment No. 86

~ ~

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f5 N

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situ uma!'

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-45, j-s*

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a 4g g

=

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M*

a 5.

co DAVIS-BESSE NUCLEAR POWER STATION UNRESTRICTED AREA B0UNDARY FOR GASEOUS EFFLUENTS Fig. 3.11-2 1

RADI0 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEQUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous affluent releases to areas at and beyond the SITE BOUNDARY (see Figure 3.11-2) would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation in a 31 day period. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY (see Figure 3.11-2) would exceed 0.3 mres to any organ in a 31 day period.

APPLICABILITY: At all times.

ACTION:

a.

With the gaseous waste being discharged without treatment and in excess of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1.

Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reasons for the inoperability, 2.

Action (s) taken to restore the inoperable equipment i

to OPERABLE status, and 3.

Summary description of action (s) taken to prevent a recurrence.

)

i b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

l SURVEILLANCE REOUIREMENTS l

4.11.2.4 When systems are not being utilized, doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters l

in the 00CM.

l l

DAVIS-BESSE, UNIT 1 3/4 11-16 Amendment No. 86

.e

t.

RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE (Hydrogen rich systems not designed to withstand a hydrogen explosion) i LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas system shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICA8ILITY: At all times.

ACTION:

a.

With the concentration of oxygen in the waste gas system greater than 2% by volume but less than or equal to 4%

by volume, reduce the oxygen concentration to the above limits, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

With the concentration of oxygen in the waste gas system greater b.

than 4% by volume and the hydrogen concentration greater than 47, by volume, immediately 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.

1 SURVEILLANCE REQUIREMENTS The concentrations of oxygen in the waste gas system shall be 4.11.2.5 detamined to be within the above limits by monitoring the waste gases in the waste gas system as rwquired by Table 3.3-16 of Specification 3.3.3.10.

DAVIS-BESSE, UNIT 1 3/4 11-17 Amendment No. 86

i 4

)

RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwasta system shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and destination burial ground requirements.

APPLICABILITY: At all times.

ACTION:

a.

With the provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS I

4.11.3 THE PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION or DEWATERING of at least one representative test specimen 'from at least 10% of the batches of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions).

If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFI-a.

CATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFI-CATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent. test verifies SOLIDIFICATION.

~

SOLIDIFICATION of the batch may then be resumed using the alterna-tive SOLIDIFICATION parameters determined by the PROCESS CONTROL

~

PROGRAM.

b.

If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION.

The PROCESS CONTROL PROGRAM shall be modified as required, as pro-vided in Specification 6.14, to assure SOLIDIFICATION of subsequent batches of waste.

s DAVIS-BESSE, UNIT 1 3/4 11-18 Amendment No.86

i RADI0 ACTIVE EFFLUENTS t

' r.

3/4.11.3 SOLID RADIOACTIVE WASTE

[

k

- SURVEILLANCE REQUIRE.' TENTS (Continued) c.

If any test specimen fails to verify DEWATERING, the DEWATERING of that batch under test shall be suspended. Alternate DEWATERING parameters can be determined using the PROCESS CONTROL PROGRAM.

If a subsequent test verifies DEWATERING, DEWATERING of the batch may be resumed using the alternative parameters determined by the PROCESS CONTROL PROGRAM.

d.

If the test specimen fails to verify DEWATERING, the PROCESS CONTROL PROGRAM shall provide for the testing of a representative specimen of the same type wet waste from consecutive batches until at least 3 test specimens demonstrate DEWATERING. The PROCESS CONTROL PRO-GRAM shall be modified as provided in Specification 6.14 to assure DEWATERING of subsequent batches of waste.

DAVIS-BESSE, UNIT 1 3/4 11-19 '

Amendment No. 86

RADI0 ACTIVE EFFLUENTS 3/4. n.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.n.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 areas to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 areas.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated doses from the release of radioactive materials in liquid or gaseous affluents exceeding twice the limits of Speci fi cati on 3. H.1. 2. a. 3. n.1. 2. b, 3. n. 2. 2. a, 3. n. 2. 2. b,

3.11.2.3.a. or 3. H.2.3.b evaluations should be made including direct radiation contributions from the reactor units and from out-side storage tanks to determine whether the above limits of Specification 3. H.4 have been exceeded.

If such is the case, in lieu of a Licensee Event Report, prepara and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources.

including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report.

It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels i

or cor.centrations.

If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

4. n. 4.-

Cumulative dose contributions from liquid and gaseous affluents shall l

be determined in accordance with Specifications 4. n.1.2, 4. n.2.2, and 4.11.2".3, and in accordance with the methodology and parameters in the 00CM.

DAVIS-BESSE, UNIT 1 3/4 11-20 Amendment No. 86 i

i 3/4.12 RADIOLOGIC'AL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM

}3(

LIMITING CONDITIONS FOR OPERATIONS 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a.

With the radiological environmental monitoring program not being

{

conducted as specified in Table 3.12-1, in lieu of a Licensee I

Event Report, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specifica-tion 6.9.1.n, a description of the reasons for not conducting the

~

program as required and the plans for preventing a recurrence.

i b.

With the level of radioactivity as the result of plant affluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to A MEMBER OF THE PUBLIC is less than the calendar year limits of Specification

3. U.1.2, 3. n.2.2, and 3. n.2.3.

When more than one of the radio-nuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2) reporting level (1)

reporting level (2) * *" 11.0 When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents,.this report shall be submitted if the potential annual dose to A MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 3.n.1.2,

3. n.2.2 and 3. n.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c.

With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and if practical add them to the radiological environmental monitoring program within 30 days. The locations from which samples were unavailable may then be deleted from the monitoring program.

In lieu of a Licensee Event Report and pursuant to Specification 6.9.1. n, identify.the cause of the unavailability of samples and identify the new location (s) for 4

obtaining replacement samples in the next Semiannual Radioactive i

Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

i DAVIS-BESSE, UNIT 1 3/4 12-1 Amendment No. 86

...a4.e%-....

- - + -

s

r..

s-RADIOLOGICAL ENVIRONMENTAL MONITORING d.

With specimens unobtainable due to hazardous conditi6ns, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons, every effort will be made to complete corrective action prior to the end of the next sampling period.

All deviations from the sampling schedule will be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.1.1.10.

e.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure (s) in the 00CM and shall be analyzed pursuant to the requirements of i

Table 3.12-1, and the detection capabilities required by Table 4.12-1.

4.12.1.2 Cumulative potential dose contributions for the current calendar year from radionuclides detected in environmental samples shall be determined in accordance with the methodology and parameters in the ODCM.

1 l.~

l l

l r

DAVIS-BESSE, UNIT 1 3/4 12-2 Amendment No.86

g, y, c'

}

+

TABLE 3.12-1 l

k itADIOLOGICAL ENVIR0004 ENTAL MONITORING PROGRAM

?

h Exposure Pathway Number of Representative Type and Frequency

,N!

and/or Sample Samples and Sample Locations, Collection Frequency of Analysis b

E 1.

DIRECT RADIATION 27 routine monitoring stations either Quarterly Gamma dose quarterly Q

with two or more dosleeters or with one instrument for measuring and g

recording dose rate continuously, j

placed as follows:

1 an inner ring of stations, generally one in each meteorological sector in the general area of the SITE BOUNDARY; an outer ring of stations, one in R

each meteorological sector in the 6-to 8-km range from the site, except the sectors over Lake Erle; la the balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 i

areas to serve as control stations.

i a

a

!F m

1 e

1 TABLE 3.12-1 (Continued)

E RADIOLOGICAL ENVIR0letENTAL HONITORING PROGRAM T

em 3

Exposure Pathway Number of Representative Type and frequency

,m and/or Sample Samples and Sample Locations, Collection Frequency of Analysis k 2.

AIRBORNE

-e H

Radiolodine and Samples from 5 locations Continuous sampler Radiolodine Cannister:

Particulates operation with sample I-131 analysis weekly.

3 samples from close to the 3 SITE collection weekly, or BOUNDARY locations, in different more frequently if sectors, generally from areas of required by dust Particulate Sampler:

higher calculated annual average loading Gross beta radioactivity groundlevel D/Q.

analysig following filter y

ch'ange; dGamma isotopic 1 sample from the vicinity of a analysis of composite nearby community, generally in the (by location) quarterly.

7' area of higher calculated annual average groundlevel D/Q.

I sample from a control location, 15-30 km distant.

3.

WATER 8ORNE a.

Surface 2 samples Weekly composite Compositefortritjun g

sample (Indicator and gamma isotopic location is a analysis monthly.

,o E.

continuous, 2

composite trickle-5 feed) d E

b.

Groisnd Sample from one source quarterly Gamma isotopic and onlyifjlkelytobe tritium analysis a,

affected quarterly.

9

4RL..heeV

,, i l

1 l

TABLE 3.12-1 (Continued)

O RADIOLOGICAL ENVIR000 ENTAL MONITORING PROGRAM U.

de O.

Exposure Pathway Number of Representative Type and Frequency

.M and/or Sample Samples and Sample tocations, Collection Frequency of Analysis E c.

Drinking 1 sample from the nearest Weekly composite Gross beta on monthly Q

source.

sample.

composite. Triting

,and gamma isotopic 1 sample from a control location analysis on quarterly composite.

I-131 analysis on each composite when the dose calculated for the consumption of j

g the water is greater a

than 1 ares per year.

h d.

Sediment from I sample from area with existing Sealannually Gamma isotopic analysisd Shoreline or potential recreational value semiannually.

4.

INGESTION d

a.

Milk If available, samples from allking Semimonthly when Gamma isotopic ad animals up to 2 locations within animals are on I-131 analysis semi-8 km distance having the highest pasture, monthly monthly when animals dose potential, at other times are on pasture; monthly at other times.

i F

4 I sample from allking animals s

at a control location 15-30 km distant and generally in a less l

a prevalent wind direction.

1 r*

's TABLE 3.12-1 (Continued)

E RADIOLOGICAL ENVIR0letENTAL MONITORING PROGRAM T

in h

Exposure Pathway Number of Representative Type and Frequency

,m and/or Sample Samples and Sample Locations, Collection Frequency of Analysis E

d U.

Fish I sample each of 2 commercially 1 sample in season.

Gamma isotopic analysis b

and/or recreationally important on edible portions.

H species in vicinity of site.

I sample of same species in areas not influenced by plant j

discharge.

c.

Food Products Samples of up to 3 different kinds Monthly when avall-Gamma isotopicd,g of broad leaf vegetation growth in able.

1-131 analysis.

two different offsite locations of higher predicted annual average j

ground-level D/Q if milk sampling l

1s not performed.

d I sample of each of the siellar Monthly when avall-Gamma isotopic ad broad leaf vegetation grown able.

1-131 analysis.

15-30 km distant in a less prevalent wind direction if 3'

milk sampilng is not performed.

an

.U r.

4 b

't 4 I

TABLE 3.12-1 (Continued)

TABLE NOTATION D

" Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and figure (s) in the 00CM. Refer to NUREG-0133, " Preparation of Radio-1 logical Effluent Technical Specifications for Nuclear Power Plants".

October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979.

It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.

In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.11, identify the cause of the unavailability of samples for that pathway and identtfy the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the 00CM reflecting the new location (s).

b0ne or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.

Film badges shall not be used as dosimeters for measuring direct radiation.

The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout for TLD systems will depend upon the char-

~

acteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

CAirborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay.

If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

dGamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the facility.

' Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

i DAVIS-BESSE, UNIT 1 3/4 12-7 Amendment No. 86

l TABLE 3.12-2 REPORTINGLEVELSFORilADI0ACTIVITYCONCENTRATIONSINENVIR0004ENTALSAMPLES Reporting Levels C.

v" Water Airborne Particulate Fish Milk Vegetables g

Analysis (pCl/1) or Gases (pC1/m )

(pC1/kg, wet)

(pCl/1)

(pCl/kg, wet) 8 M

,H-3 2 x 104*

g Mn-54 1 x los 3 x 104 Fe-59 4 x 108 1 x 104 Co-58 1 x 10s 3 x 104 Co-60 3 x 108 1 x 104 w1 2n-65 3 x 108 2 x 104

_mb Zr-Nb-95 4 x 108 1-131 2

0.9 3

1 x 108 Cs-134 30 10 1 x 108 60 1 x los Cs-137 50 20 2 x 108 70 2 x 10s R

Ba-La-140 2 x 108 3 x los E

g-

"For drinking water samples, this is the 40 CFR 141 value.

If no drinking water g

. pathway exists, a value of 30,000 pCl/ liter may be used.

O N

9 w

d

.c

^1g, -

l

'1 s

TABLE 4.12-1 E

LOWER LIMITS OF DETECTION (LLD)*

u 4O Airborne Particulate N

Water Or Gas Fish Milk Food Products Sediment Analysis (pCl/1)

(pCl/m )

(pC1/kg, wet)

(pCl/1)

(pCl/kg, wet)

(pC1/kg, dry) 8 cz l.

O Gross Beta 4

1 x 10-8 i

e C

3 2000 "

H l

54 15 130 h

59 30 260 Fe 58, 60 15 130 Co 65,

30 260 7

95 15 Zr d

131 I

-7 x 10-8 1

60 l

g b

134, 137 15(10 ),18 6 x 10-8 130 15 60 150 i

Cs j

k 140 15 15 8a E

2 a

NOTE: This IIst does not mean that only these nuclides are to be detected and reported.

E Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified and reported.

E

If no drinking water pathway exists, a value of 3000 pCi/L may be used.

i a

TABLE 4.12-1 (Continued)

, TABLE NOTATION a.

The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 s LLD =

b E

V 2.22 Y

exp(-Aat)

~

where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume).

~

s is the standard deviation of the background counting rate 3 or of the counting rate of a blank sample as appropriate (as counts per minute).

E is the counting efficiency (as counts per transformation).

V is the sample size (in units of mass or volume).

2.22 is the number of transformations per minute per picoeurie.

Y is the fractional radiochemical yield (when applicable).

A is the radioactive decay constant for the particular radionuclide.

At is the elapsed time between end of the sample collection period and time of counting.

l Typical values of E, V, Y and at should be used in the calculations.

l o

l I

DAVIS-BESSE, UNIT 1 3/4 12-10 Amendment No.86 I

,--_m

TABLE 4.12-1 (Continued)

TABLE NOTATION The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a, posteriori (after the fact) limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of inter-fering nuclides, or uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

For more complete discussion of the LLD and other detection limits, see the following:

_ (1) HASL Procedures Manual, HASL-300 (revised annually)'.

~

(2) Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques", Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

b.

LLD for drinking water.

If no drinking water pathway exists, a value of 3000 pCi/ liter c.

may be used.

d.

LLD only when specific analysis for I-131 required.

s DAVIS-BESSE, UNIT 1 3/4 12-11 Amendment No. 86

A 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITIONS FOR OPERATIONS 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological l

sectors of the nearest milk animal, the nearest residence and the nearest 2 (500 ft ) producing broad leaf vegetation.

2 garden of greater than 50 m APPLICABILITY: At all times.

ACTION:

a.

With a land use census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of a Licensee Event Report, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.11.

b.

With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure l

pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) if practical to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having a lower calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program. In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.11, identify the new location (s) in the next Semiannual Radioactive l

Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS l

4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by l

consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmentti Operating Report pursuant to Specification 6.9.1.10.

DAVIS-BESSE, UNIT 1 3/4 12-12 Amendment No. 86

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.

APPLICABILITY: At all times.

ACTION:

a.

With analyses not being performed as required above, report the ct..rective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.10.

~

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radio-logical Environmental Operating Report pursuant to Specification 6.9.1.10.

1 DAVJS-BESSE, UNIT 1 3/4 12-13 Amendment No. 86

b'

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i Bases Fleure 3-2 incore Instrumentadon Specification i

Acceptable Mininwm OUADRANT POWER TILT Anangement DAVIS-BESSE, UNIT 1 B 3/4 3-5

INSTRUMENTATION BASES 3/4.3.3.9 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with methods in the 00CM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

3/4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous affluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with methods in the 00CM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system.' The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

i l

l l

l I

I DAVIS-BESSE, UNIT 1 B 3/4 3-6 Amendment No.85 I

___,_.,m_.

= _

V.

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20.106. This limitation as implemented by the ODCM pro-vides additional assura.ee that the levels of radioactive materials in bodies of water outside the site should not result in exposures exceeding (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population.

The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisetope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in. International Commission on Radiological Protection (ICRP) Publication 2.

3/4.11.1.2 DOSE This specification is provided to implement the requirements of Sections II.A III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Aopendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid affluents will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the 00CM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by cal-1 -

culational procedures based on modes and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the 00CM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977.

i e

DAVIS-BESSE, UNIT 1 B 3/411-1 Amendment No. 86

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

~

l RADI0 ACTIVE EFFLUENTS 4

BASES 3/4.11.1.3 LIQUID WASTE TREATMENT

'(I i

The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General i

Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section II.D of Appendix A to 10 CFR Part 50. Based on a cost analysis of treating liquid radwaste, the specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as the dose design objectives as set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

3/4.11.1.4 LIQUID HOLDUP TANKS t

Restricting the quantity of radioactive material contained in the i

specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.

(

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j DAVIS-BESSE, UNIT 1 B 3/411-2 Amendment No.86

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose at the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix 8. Table II.

These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a member of the public outside the site boundary to annual average con-centrations exceeding the limits specified in Appendix 8. Table II of t

10 CFR Part 20 (10 CFR Part 20.106(a)). For members of the public who may at times be within the site boundary, the occupancy of that member of the public will be sufficiently low to compensate for any increase in the atagspheric diffusion factor above that for the site boundary.

The specified release limits restrict the corresponding gamma and beta doses above background to an individual at or beyond the unrestricted area boundary to i 500 ares / year to the total body or to < 3000 mram/ year to the skin. These release limits also restrict, at all times, the corresponding thyroid doses above background to a child via the inhalation pathway to i 1500 aren/ year.

]

l 04VIS-8 ESSE, UNIT 1 B 3/4 11-3 Amendment No. 86

Pd. '

RADIOACTIVE EFFLUENTS h'-

BASES r

3/4.11.2.2 DOSE, NOBLE GASES This specification is provided to implement the requirements of Sections II.8, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of. radioactive material in gaseous affluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I ta be shown by calculation procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the 00CM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109,

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, " Revision 1, October 1977 and Regulatory Guids 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.

DAVIS-BESSE, UNIT 1 B 3/4 11-4 Amendment No. 86 e

1 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.3 00SE, RADICIODINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexi-bility and at the same time implement the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The 00CM calculational methods specified in the surveillance requirements implement the requirements in Section III. A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Reg ~ulatory Guide 1.109, " Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

i Revision 1. July 1977.

The release rate specifications for radiciodines, radioactive material in particulate form and radionuclides other than noble gases are dependent t

on the existing radionuclide pathways to man, in the unrestricted area.

l The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of

(

radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposi-tion on the ground with subsequent exposure of man.

. ~ ~

3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The requirements that the appropriate port'u ! of these systems be used, when specified, provides reasonable assuiirc4 that the releases of radioactive materials in gaseous eff"VFei v' 1 be kept "as low as reasonably achieveable". This specift sts'1 'aplements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous affluents.

DAVIS-BESSE, UNIT 1 B 3/4 11-5 knendment No. 86

_m

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification 'is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treatment system is maintained below the flammability limits of hydrogen with oxygen. Maintaining the concentration of hydrogen or oxygen below their flammability limits provides assurance that the releases of radio-active materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4.11.3.

SOLIO RADIOACTIVE WASTE The requirements for solid radioactive waste handling and disposal given under this specification provide assurance that solid radioactive materials shipped offsite, meet destination disposal site requirements and are packaged in conformance with 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Paits 170-178.

s DAVIS-BESSE, UNIT 1 B 3/411-6 Amendment No.86 1

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.4 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525.

l The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive affluents and direct radiation axceed 25 mress to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 areas.

For sites containing up to 4 reactors, it is highly unlikely that

~

the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part.190 if, the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small.

~

The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius l of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications 3.11.1.1 and 3.11.2.1.

An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any l

operation that is part of the nuclear fuel cycle.

1 l

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s DAVIS-BESSE, UNIT 1 B 3/4 11-7 Amendment No.86 I

i i

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this specification pro-vides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by measuring concentrations of radioactive materials and levels of radiation which may be compared with those expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 2 provides

50. Restricting the census to gardens of greater than 50 m assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regualtory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: 1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce 2

and cabbage), and 2) a vegetation yield of 2 kg/m,

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Compari-son Program is provided to ensure that' fndependent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

DAVIS-BESSE, UNIT 1 B 3/412-1 Amendment No. 86 1

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3...

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 Specificationt e.

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

~~~

f.

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

~

g.

Review of facility operations to detect potential safety hazards.

h.

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

Review of the Plant Security Plan and implementino precedures and shall submit recormended changes to the Chairman of the

. Company Nuclear Review Board.

j.

Review of the Emergency Plan and implementing procedures and shall submit reconnended changes to the Chairwan 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 identified to prevent recurrence, review of a report covering the evaluation and forwarding of the report to the Station Superintendent and to the CNRB.

1.

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

Review of the PROCESS CONTROL PROGRAM and implementation of m.

procedures for processing 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.

o.

DAVIS-BESSE, UNIT 1 6-7 Amendment No. 27,86

ADMINISTRATIVE CONTROLS 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 minutes of tach meeting and copies shall be provided to the Vice President, Nuclear and Chairnan of the Company Nuclear Review Beard.

6.5.2 COMPANY NUCLEAR REVIEW BOARD (CNRB)

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

i Nuclear power plant operations, a.

b.

Nuclear engineering, Chemistry and radiochemistry, c.

d.

Metallurgy, Instrumentation and control, e.

f.

Radiological safety, j

g.

Mechanical and electrical engineering, and h.

Quality assurance practices.

l DAVIS-BESSE, UNIT 1 6-8 Amendment No. 27, 86

,,ADMINb i<ATIVE CONTR0!.5 g-

, AUDIT 5 h.

5.5.2.8 Audits of facility activities shall be perfomed under the

{

cognizance of the CNR3. Tnese audits shall encompass:

a.

The conformance of unit coeration to provisions contained within the Technical Spe:ifications and applicable license conditions at_least once per 12 months.

b.

The periomance, training and cusiffications of the entire station staff at least once per 12 months, c.

The results of actions taken to corre:t deficien:ies c: curring in unit ecuipment, structures, systems or meth:d of coeration that afinct nu:1 ear saisty at ienst once per 5 months.

d.

The perfor:ance of activities recuired by the Duality Assurance Program to meet the criteria of Appendix "3",10 CFR 50, at least once per 24 months.

The Station Emerpency Plan and i=clementin; crece:ures at e.

ieast once ver 12 =enths.

f.

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

g.

Any other area of facility operation c:nsidered appro:riate by the CNRB.

h.

The Facility Fire Protection Program and i=clementing procedures at least once per 24 months.

An indeoendent fire prote: tion and loss prevention program i.

inspection and audit shall be cerformed at least once per 12 months utilizing either cualified offsite licznsee per-sonnel or an outside fire pr:tection fim.

j.

An inspe: tion and audit of the fire prote: tion and loss pre ~

'vention program shall be perfomed by a cualified curside fire consulant at least once per 35 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 Amendment No. 72, 27, 74, 86

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1 ADMINISTRATIVE CONTROLS AUTHORITY 6.5.2.9 The Company Nuclear Review Board shall report to and advise the 4.

President and Chief Operating Officer on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

i RECORDS 6.5.2.10 Records of Company Nuclear Review Board activities shall be prepared, approved and distributed as indicated below;

~

a.

Minutes of each CNRB meeting shall be prepared, approved and forwarded to the President and Chief Operating Officer and CNRB members within 14 days following each meeting.

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b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the President and Chief Operatin~g Officer and CNRB memoers within 14 days following completion of the review.

Aud'*. reports encomoassed by Section 6.5.2.8 above, shall be c.

forwarded to the President and Chief Operating Officer and CNRS members and to the management positions resconsible for the areas audited within 30 days after comoletion of tne audit.

4.6 REFGRTABLE OCCURRENCE ACTION 4

6. 6.1 The.following actions shall be taken for REPORTABLE OCCURRENCES:

a..

The Comission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b.

Each REPORTABLE OCCURRENCE recuiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification J

to the Comission snall be reviewed by the SRB and submitted i

to the CNRB.

1

-g 4

lAVIS-BESSE. UNIT 1 6-12 AmendmentNo.JZ,[86

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ADMINISTRATIVE CONTROLS 6.7 SARTY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The facility shall be placed in at least HOT STANDBY within one hour, b.

The Safety Limit violation shall be reported to the Comission, the Vice President Nuclear and to the CNRB within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SRB. This report shall describe (1) applicable circumstances preceding the violation (2) effects of the violation upon facility components, systems or

~

structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Comission, the CNRS and the Vice President, Nuclear within 14 days of the violation.

5.8 DDOCE "REE 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below:

a.

The applicable procedures recomended in Appendix "A" of Regulatory Guide 1.33, November, 1972.

b.

Refueling operations.

~

Surveillance and test activities of safety related equipment.

c.

d.

Security Plan implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

g.

The radiological environmental monitoring program.

h.

The Process Control Program.

i.

Offsite Dose Calculation flanual implementation.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall 'be reviewed by the SRB and approved by the Station Superintend.ent prior i

to implementation and reviewed periodically as set forth in administrative procedures.

DAVIS-BESSE, UNIT 1 6-13 Amendment No. 9, 77, 27,86 i

r - - -

r ADMINISTRATIVE CONTROLS -

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

The intent of the original procedure is not altered, s.

b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactar Operator's License on the unit affected.

The change is documented, reviewed by the SRB and approved

~

c.

by the Station Superintendent within 14 days of implementation.

6.0.4 The following procrams shall be established, impiemented, and maintained:

a.

Priman Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include makeup, letdown, seal injection, seal return, low pressure injection, containment spray, high pressure injection, waste gas, primary sampling and reactor coolant drain systems. The program shall include the following:

(1) Preventive maintenance and/or periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

b.

In-Plant Radiation Monitoring A program which will ensure the capability to accurately deter-mine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

(1)

Training of personnel, (ii)

Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis eouip-ment.

DAVIS-BESSE, Uti!T 1 6-14 Amenoment No. f f) C 51

4

' WTN!5TRATTV! CONTROLS Failure or. malfunction of one or more components which prevents s'

s.

or could prevent. by itst]f.*the fulfillment of the functional requirements of system (s) used to cope with accidents analyzed in the SAR.

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7 f.

Personnel error or procedural inadequacy which prevents or emuld prevent. by itself, the fulfillment of the functional require-ments of'systans required to ^ cope with accidents analyzed in the SAR.

g.

Conditioris arising fras natural or man-made events that, as a direct result of the event require plant shutdown, operation of safety systams, or other protective measures required by technical specifications.

h.

Errors discovered in.the transient or accident analyses or in the methods used for such anilyses.as described in the safety analysis report or in the bases for the technical specifications that have or cmuid have permitted reactor operation in a manner 1ess conservat.iverthan assumed in the analyses.

1.

Firformance of structures, systnes, or ccmoonents that re:uires reedia) a:: ion or c:rrective measures to prevent coera:1:n in :a manner less conservative than assumed in the a=1 den:

analyses in :ne safe:y analysis recor: or technt:a1 see:1 fica-tions sases; or discsvery during plant If fe of conditions not see:ifically consicered in the safety analysis recor: or te:nnical specifica:icos that require remedial a:: ion or =r.

rective measur=_s :s prevent the existence or develc;=ent of :n unsafe condi: ion.

ITHiUY DAY V:.iWIN 2.E?DRTS 6.5.1.9 The tyees of events listed below shall be the subje:: of wrt :en re:sr:s to tne of re:::r of the Regional Office within thirty days of scurrence of the event. The wrt :en report shall in:1ude, as a = int =:.s, a c= Dieted c:py of a licensee event re::rt fem. Inf rmation provided on :ne Itcensee event re::r: f:rm snall be supplemented, as needed, by additional narrative material to provide ec=plete explanation of :ne cir-~ ances surrounding the event.

a.

Ana: or prc:ection system or engineered safety fez ure instru-ment settings which are f:und to be less unservative than

nose established by the technical specifications but wnich do not prevent the fulfillment of the fun::14nal requirements of affe:ted systa=s.

Amendment No.&, 54 CMIS-?IsIE, UNIT 1 6-17

' Routine surveillance testinD, instrument calibration, or preventive maintenance which reoutre system configurations as described in Se: tion 6.9.1.9.a and 6.9.1.9.b need not be reported except where test resu1*s themselves reveal a degraded condition requiring corrective action.

i

_,__,____,,,_._...,-___,_,,_,__,,______.,.__,__,,,.,,,m

i ADf1INISTRATIVE CONTROLS b.

Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.

c.

Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems i

or engineered safety feature systems.

d.

Abnormal degradation of systems other than those specified in 6.9.1.8.c above designed to contain radioactive material resulting from the fission process.

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 May 1 of each year. The initial report shall be submitted prior i

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 radiological environmental surveillance activities for the report period, including a comparison with the preoperational studies, with operational controls, as appropriata, and with previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land u - -'nsuses required by Specification 3.12.2.

i The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all t

environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the 00CM, as well as summar-ized 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 be 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 monitoring program; at least two legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory 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.

1 l

l OAVIS-BESSE, UNIT 1 6-17a Amendment No. 86 l

i

y n ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.11 Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January I and July 1 of each year. The period of the first report shall begin with the date of initial criticality.

The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous affluents and solid wasta released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,". Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous affluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figures 3.11-1 and 3.11-2) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included.in these re;: orts. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

DAVIS-BESSE, UNIT 1 6-17b Amendment No.86 n

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) 4 The Radioactive Effluent Release Reports shall include the fo114 wing information for each class of solid waste (as defined by 10 CFR Part 61) sNtpped offsite during the report period:

a.

Container volume, b.

Total curie quantity (specify whether determined by measurement or estimate),

c.

Principal radionuclides (specify whether deterinined by measurement or estimate).,

d.

Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

_. e.

Type of container (e.g., Type A, Type B, Large Quantity), and f.

Solidification agent or absorbent (e.g., cement, urea formaldehyde).

The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid affluents made during the reporting period.

The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (00CM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

s DAVIS-BESSE, UNIT 1 6-17c Amendment No. 86

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I ADMINISTRATIVE CONTROLS SPECIAL REPORTS 4

p.9.2 Special reports shall be submitted to the Director of the Office bf, Inspection and Enforcement Regional Office within the time pqriod 1

specified for each report. These reports shall be submitted covering c

l

.the activities identified below pursuant to the requirements of the applicable reference specification:

j ECCS Actuation, Specifications 3.5.2 and 3.5.3.

a.

b.

Inoperable Seismic Monitoring Instrumentation, Specification i

3.3.3.3.

Inoperable Meteorological Monitoring Instrumentation, c.

Specification 3.3.3.4.

d.

Seismic event andlysis, Specification 4.3.3.3.2.

I e.

Fire Detection Instrumentation, Specification 3.3.3.8.

l f.

Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2.

_g.

Fire Barrier Penetrations, Specification 3.7.10.

~

h.

Dose or dose commitment exceedences to a MEf1BER 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 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.

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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 Specification 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 e

Specification 3.11.4.

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

in an environmental sampling medium exceeding the reporting levels of Table 3.12-2 (Specification 3.12.1).

DAVIS-BESSE, UNIT 1 6-18 Amendment No. 7,' 72, H,86 e

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ADf11NISTRATIVE CONTROLS s

G.10 RECORD RETENTION 5

6.10.1 The following records shall be retained for at least five years:

. lf a.

Records and logs of facility operation covering time interval

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at each power level.

I b.

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

c.

ALL REPORTABLE OCCURRENCES submitted to the Commission.

d.

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

r DAVIS-DESSE, UNIT 1 6-18a Amendment No. 85 t

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ADMINISTRATIVE CONTROLS e

e.

Records of changes made to Operating Procedures.

f.

Records of radioactive shipments.

I I

Records of sealed source and fission detector leak tests g.

and results.

h.

Records of annual physical inventory of all sealed source mater 31 of record.

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 modifi-cations made to systems and equipment described in the Final

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i Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

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Records of radiation exposure for all individuals entering c.

radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

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e.

Records of transient of operational cycles for those facility components identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

g.

Records of training and qualification for current members of the plant staff.

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h.

Records of in-service inspections perfomed pursuant to these Technical Specifications.

1.

Records of Quality Assurance activities required by the QA Manual.

j.

Records of reviews performed for changes made to procedures or equipment 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 o

j the provisions of paragraph 6.13.

Amendment No. K. 3[,1980 6-19 DAVIS-8 ESSE, UNIT 1 Order ~dtd. Oct. 24, i

a 2

i ADMINISTRATIVE CONTROLS RECORD RETEIRION (continued) 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 procedures were followed.

(

)

DAVIS-BESSE, UNIT 1 6-19a.

Amendment No. 86 l

i J

t ADMINISTRATIVE CONTROL i

6.13 ENVIRONMENTAL OUALIFICATION 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 Ele'etrical Equipment in Operating Reactors"(DOR Guidelines) 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.

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6.13.2.By no later than December 1,1980, complete and auditible records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipnent in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tgsted.

-or otherwise further qualified.

DAVIS-BESSE, UNIT 1 6-21 Order dated October 24, 1980

ADMINISTRATIVE CONTROLS 6.14 PROCESS CONTROL PROGRAM (PCP) 6.14.1 Licensee initiated changes to the PCP:

1.

Shall be submitted to the Commission in the Sesiannual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:

a.

Information to support the rationale for the change; b.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.

Documentation of the fact that the change has been reviewed and found acceptable by the SR8.

2.

Shall become effective as reviewed and accepted by the SR8.

6.15 0FFSITE DOSE CALCULATION MANUAL (00CM) 6.15.1 Licensee initiated changes to the 00CM:

I 1.

Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain:

a.

Information to support the rationale for the change; b.

A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; j

and

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c.

Documentation of the fact that the change has been reviewed and found acceptable by the SRS.

j 2.

Shall become effective as reviewed and accepted by the SRB.

DAVIS-BESSE, UNIT 1 6-22 Amendment No. 86 L

. ADMINISTRATIVE CONTROLS 6.16 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SY5ItMS j

6.16.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid):

1.

Shall be reported to the Commission in the update to the Safety Analysis Report. The discussion of

)

each change shall contain:

a.

A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59; b.

Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c.

A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; d.

An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; e.

An evaluation of the change, which shows the expected maximum exposures to individual in the UNRESTRICTED AREA and to the general population that differ

.~~

from those previously estimated in the license application and amendments thereto; f.

A comparison of the predicted releases of radioactive materials, in liquid and gaseous affluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; g.

An estimate of the exposure to plant operating personnel as a result of the change; and DAVIS-BESSE, UNIT 1 6-23 Amendment No. 86

ADMINISTRATIVE CONTROLS 6.16 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASEOUS, AND SOLID WASTE j

TREATMENT SYSTEMS (Continued) h.

Documentation of the fact that the change was reviewed and found acceptable by the Station g

Review Board.

2.

Shall become effective upon review and acceptance by the Station Review Board.

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DAVIS-BESSE, UNIT 1 6-24 Amendment No. 86 lO h.

1 DB-1 ENVIRONMENTAL TECHNICAL SPECIFICATIONS TABLE OF CONTENTS PAGE LIST OF TABLES........................

iii LIST OF FIGURES iv 1.0 DEFINITIONS 1.0 2.0 LIMITING CONDITIONS FOR OPERATION 2.1-1 2.1 (Deleted) 2.2(Deleted) 2.3 (Deleted) 2.4(Deleted) 3.0 ENVIRONMENTAL SURVEILLANCE..................

3.1-1 3.1 Non-radiological Surveillance..............

3.1-1 3.1.1.a (Deleted) 3.1.2.a(Deleted) 3.1.2.b Biotic - Terrestrial 3.1-12 3.2 (Deleted) 4.0 S'PECIAL SURVEILLANCE, AND STUDY ACTIVITIES..........

4.1-1 4.1 Operational Noise Surveillance 4.1-1 4.2 (Deleted) 4.3 (Deleted)

Amendment No. 36, Pf,86 i

DB-1 ENVIRONMENTAL TECHNICAL SPECIFICATIONS LIST OF TABLES Table Number Title g

2.4-1 (Deleted) 2.4-2 (Deleted) 2.4-3 (Deleted) 2.4-4 (Deleted) 2.4-5 (Deleted) 3.1-1 (Deleted)

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3.2-1 (Deleted) 3.2-2 (Deleted) 3.2-3 (Deleted)

Amendment No, ff, 86 iii

DB-1 ENVIRONMENTAL TECHNICAL SPECIFICATIONS LIST OF FIGURES Figure Number Ti tle Page 3.1-1 (Deleted) 3.2-1 (Deleted) 3.2-2 (Deleted) 3.2-3 (Deleted)

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Amendment No. JSP, 86 iv f

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DB-1 1

1 2.0 LIMITING CONDITIONS FOR OPERATION 1 -

2.1 (Deleted) i 2.2 - (Deleted) e 2.3 (Deleted)'

2.4 (Deleted) i i

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AmendmentNo,f/,86 2.1-1 4

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DB-1 3.0 ENVIRONMENTAL SURVEILLANCE 3.2 (Deleted)

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Amendment No. 86 3.2-1 i

I

DB-1 5

5.0 ADMINISTRATIVE CONTR01.S 5.4 Unit Reporting Requirements 5.4.1 Routine Reports A.

Annual Environmental Operating Report Part A - Nonradiological Report - A report on the environmental surveillance programs for the previous 12 months of operation shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document within 90 days af ter January 1 of each year. The period of the first report shall begin with the date of commercial operation. The report shall include descriptive summaries and presentation of results, if available, of the special sur-veillance and study activities (Section 4), summaries, interpretations, and statistical evaluation of the results of the nonradiological environmental i

surveillance activities (Section 3) and the environmental monitoring pro-grams required by limiting cond.tions for operation (Section 2) for the report period, including a comparison with preoperational studies, opera-I tional controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the unit operation on the environment. In the event that some results are not available with-

~in the 90 day period, the report shall be submitted noting and explaining the reason for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. If harmful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the problem and a proposed course of action to alleviate the problem.

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5.4-1 Amendment No. 86 i

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DB-1 1

B.

(Deleted) 1

.4.2 Nonroutine Reports A.

Montoutine Envire. mental Operating Reports A report shall be submitted in the event that (a) a limiting condition for operation is exceeded (as specified in Section 2 " Limiting Conditions for Operation"), or (b) an unusual or i=portant csent occurs that causes a sig-nificant environmental impact, that af fects potential enviro:cental impact frca unit operation, or that has high public or potential public interest concerning environmental i= pact from unit operation.

Reports shall be sub-mitted under the report schedule described below:

1.

Prompt Report.

Those events requiring prompt reports shall l

be reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone, telegraph, or l

f acsimile transmission to the Director of the NRC Regional Office and within 10 days by a written report to the Director of the Regional NRC Office (with a copy to the Director, Office of Nuclear Reactor Regulation).

2.

30-Day Report.

Those events not requiring prompt reports shall be reported within 30 days by a written report to the Director of the 2.RC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation).

The reporting schedule for reports concerning limiting conditions for operation specified in Section 2.4.1.a and Section 2.4.3.a and in (b) above shall be on the pro =pt schedule.

A=endment No. g, 86

DB-1 The significance of an unusual or apparently important event with regard to environmental impact may not be obvious or fully appreciated at the time of In such cases, the NRC shall be informed promptly of changes occurrence.

in the licensee's assessment of the significance of the event and a corrected report shall be submitted as expeditously as possible.

B.

(Deleted) c.

(Deleted) l 1

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i 5.4-3 Amendment No. 85

DB-1 1

5.4.3 Chance in Environmental Technical Specifications A.

A report shall be made to the NRC prior to implementation of a

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change in unit design, in unit operation, or in procedures de-scribed in Section 5.3 if the change would have a significant ef fect on the environment or involves an environmental matter or l

question not previously reviewed and evaluated by the NRC. The i

report shall include a description and evaluation of the change and a supporting benefit-cost analysis.

B.

Request for changes in environmental technical specifications shall be submitted to the Director, Office of Nuclear Reactor Regulation, for review and authorization. The request shall include an evalua-tion of the environmental impact of the proposed change and a supporting benefit-cost analysis.

h 5.4-4 Amendment No. 86

DB-1 5.0 ADMINISTRATIVE CONTROLS 5.5 Records Retention 5.5.1.

Records s'nd logs relative to instrument calibration and chemical analysis shall be retained for five years except as described in Section 5.5.2.

5.5.2 All records and logs relative to the following areas shall be retained for the life of the unit:

5.5.2.1 Records and drawing changes reflecting unit design modifica-tions made to systems and equipment described in the unit's Environmental Report.

5.5.2.2 Records of environments 1 monitoring surveys.

i 5.5.2.3 (Deleted) 5.5.2.4 Min 6tes of Station Review Board and Company Nuclear Review Board meetings.

5.5.2.5 Copies of all superseded operating procedures which affect the environment.

9 5.5-1 Amendment No.86

ML20129J696

Text

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