ML20097G803

Corrected Pages to Amend 162,revising CR Assembly Position Indication Acceptance Criteria & Amend 170,revising TS to Relocate Procedural Details of Current Radiological Effluent TS to License NPF-3

ML20097G803
Person / Time
Site:	Davis Besse
Issue date:	06/08/1992
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20097G806	List: ML20097G803
References
NUDOCS 9206170316
Download: ML20097G803 (18)

Text

{{#Wiki_filter:._ _ _ _. _ _ _ _ _ _ _ _ - _ - - - d e* RIACTIVITT C0!TTROL SYSTEMS b BASES 3/4.1.2 BORATION SYSTEMS (Continued) stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable. The boron capability required belov 200'F is sufficient to prnvide a SHUTDOVN MARGIN of 1% 6k/k af ter menon decay and cooldown from 200'F to 70'F. This condition requires either 600 gallons of 7875 ppe borated vater from the boric acid storage system or 3,000 gallons of 1800 ppa borated water from the borated water storage tank. The botton 4 inches of the borated vater storage tank are not available, and the instrumentation is calibrated to reflect the available volume. All boric acid tank volume is available. The limits on water volume, and boron concentration ensure a pH value of between 7.0 and 11.0 of the solution recirculated within containment after a design basis accident. The pH band minimises the evolution of iodine and nintaises the effect of chloride and caustic stress corrosion cracking on mechanical systans and components. The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6. 3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section (1) ensure that acceptable pow MARGIN is maintained, and (3) limit the potential effects of a red . ejection accident. OPERABILITT of thq control rod position indicators is required to determine control rod positions and'thereby ensure compliance with the control rod alignment and insertion 11asts.. The ACTION statements which permit limited variations from the basic-requirements are acccupanied by additional restrictions which ensure

t. hat the original criteria are net.

For example, misalignment of a safety or regulating rod requires a restriction in THERMAL POVER. reactivity wortn et a assaligned rod is 11mited for the remainder of the The fuel cycle to prevent exceeding the assumptions used in the safety analysis. The position of a rod declared inoperable due to misalignment should not be included in computing the average group position for determining the CPERABILITY of rods with lesser aisalignments. DAVIS-BESSE, UNIT 1 B 3/4 1-3 Amendment No. 123 9206170316 920608 PDR ADOCK 05000349 p PDR

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.3. MOVABLE CNTROL ASSEMBLIES (Continued) The maximum rod drop time permitted is consistent with the assumed rod drop time used in the safety analyses. Measurement with T > 525'F and with reactor coolant. pumps operating ensures that the meas 0ESd drop times will be representative of insertion times experienced during a reactor trip at operating conditions. Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours with frequent verifications required if 7.n automatic monitoring channel is inoperable. These verification frequcacies are adequate for assuring that the applicable LCO's are satisfied. A 1.5% group average position uncertainty is applied to the rod index curves. Therefore, the position indicators must be capable of supporting this accuracy. The Surveillance Requirement ensures this accuracy by keeping the RPI calibrated to a "known" position as indicated by the API. Using the API as a "known" position is valid provided two consecutive reed switches are not inoperable. Having one entire string (i.e., every other reed switch) inoperable is acceptable. A specific surveillance of-the reed switches is not required because:

1) When one or more reed switch fails closed, a large API indication of asymmetry occurs.

2) Two failed open reed switches in series result in a large indication of asymmetry.

3) Failed open reed switches not in series (up to every other switch) are bounded by the analysis.

Therefore, a reed switch condition not bounded by the~ analysis will be indicated by API system asymmetry indications. Technical Specification 3.1.3.8 provides the ability to prevent excessive power peaking by transient xenon at RATED THERMAL POWER. Operating restric-tions resulting from transient xenon power peaking, including xenon-free startup, are inherently included in the limits of Sections 3.1.3.6-(Regulating Rod Insertion Limits), 3.1.3.9 (Axial Power Shaping Rod Insertion Limits), and 3.2.1 (Axial Power Imbalance) for transient peaking behavior bounded by the following factors. For the period of cycle operation where regulating rod groups 6 and 7 are allowed to be inserted at RATED THERMAL POWER, an 8% peaking increase is applied at or above 92% FP. An 18% increase is applied below 92% FP. For operation where only regulating rod group 7 is allowed to be inserted at RATED THERMAL POWER, a 5% peaking increase is applied at or above 92% FP and a 13% increase is applied below 92% FP. DAVIS-BESSE, UNIT 1 B 3/4 1-4 Amendment No. AE 162

1NDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS DEFINED TERMS................................................ 1-1 THERMAL P0WER................................................ 1-1 RATED THERMAL P0WER.......................................... 1-1 OPERATIONAL M0DE............................................. 1-1 ACTI0N....................................................... 1-1 OPERABLE - OPERABILITY....................................... 1-1 REPORTABLE EVENT............................................. 1-2 CONTAINMENT INTEGRITY........................................ 1-2 CHANNEL CALIBRATION.......................................... 1-2 CHANNEL CHECK................................................ 1-2 CHANNEL-FUNCTIONAL TEST...................................... 1-3 CORE ALTERATION.............................................. 1-3 SHUTDOWN MARGIN.............................................. 1-3 IDENTIFIED LEAKAGE........................................... 1-3 UNIDENTIFIED LEAKAGE......................................... 1-4 PRESSURE BOUNDARY LEAKAGE.................................... 1-4 CONTROLLED LEAKAGE........................................... 1-4' QUADRANT POWER TILT.......................................... 1-4 DOS E E QU I V AL E NT I - 131........................................ 1-4 E-AVERAGE' DISINTEGRATION ENERGY.............................. 1-4 STAGGERED TEST BASIS..................... 1-5 FREQUENCY.N0TATION........................................... 1-5 . AXIAL POWER IMBALANCE........................................ 1-5 SHI EL D BUILDING INTEGRITY.................................... 1-5 REACTOR PROTECTION SYSTEM RESPONSE TIME...................... 1-5 SAFETY FEATURE RESPONSE TIME................................. 1-6 PHYSICS TESTS................................................ 1-6 STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIME..... 1-6 l PROCESS CONTROL PR0 GRAM...................................... 1-6a DAVIS-BESSE, UNIT 1 1 Amendment No. 3B, 86, 93,170 l .1 m--+, h._-._.-_______ _____.____-.__._______m. _.u__ ._m___ .1.'_.2_._m.._.._m__h___i.

INDEX ~ DEFINITIONS SECTION PAGE 1.0 DEFINITIONS (Continued) 1 0FFSITE DOSE CALCULATION MANUAL (0DCM)........................ 1-6a l MEMBER ( S ) 0F THE PUBL I C....................................... 1 - 6a i S I T E B 0 VN DARY......... -........................................ 1 - 6 a l UN RE ST R I CT E D ARE A.........'.................................... 1 - 6b I CORE OPERAT ING L IMITS REP 0RT.................................. 1 -6b l OPERATIONAL MODES (TABL E 1.1 )................................. 1-7 FREQUENCY NOTATION (TABLE 1.2).................................-1-8 t DAVIS-BESSE, UNIT 1 la Amendment No. 86 Jff,170

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 BORATION CONTROL Shutdown Margin........................................ 3/4 1-1 Bo ron Di l u t i on.........................................

3/ 4 1 - 3 Moderator Temperature Coef ficient....................... 3/4 1-4 Minimum Temperature for Criticality...................... - 3/4 1-5 3/4.1.2 B0 RATION SYSTEMS Fl ow Pa ths - Shu tdown.................................. 3/ 4 1-6 Fl ow Pa ths - Opera ti ng ~................................. 3/4 1-7 Ma keup Pump - Shutdown................................. 3/ 4 1 - 9 Makeup Pumps - Opera ting............................... 3/4 1-10 Decay Heat Removal Pump - Shutdown..................... 3/4 1-11 Boric Acid Pump - Shutdown............................. 3/4 1-12 Boric Acid Pumps - Operating............................ 3/4 1-13 Borated Water Sources - Shutdown....................... 3/4 1-14 Berated Water Sources - Operating...................... 3/4 1-17 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height - Safety and Regulating Rod Groups........ 3/4 1-19 Group Height - Axial Power Shaping Rod Group........... 3/4 1-21 Posi tion Indicator Channels............................ 3/4 1-22 Rod Drop T i me.......................................... 3/4 1 - 24 Safety Rod Insertion Limit............................. 3/4 1-25 Regulating Rod Insertion Limits........................ 3/4 1-26 Ro d P rog ram -............................................ 3/ 4 1 - 3 0 Xenon Rea cti v i ty....................................... 3/4 1 -33 Axial Power Shaping Rod Insertion Limits................ 3/4 1-34 DAVIS-BESSE, UNIT L III Amendment No. 38 . - _ - ~ ---n ..~_.

INDEX-LIMITIN3 CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4. 2.1 AXI AL POWER IMBAL ANCE..................................... 3/4 2-1 3/4.2.2 NUCLEAR HEAT FLUX HOT-CHANNEL FACTOR - F................. 3/4 2-5. q N 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F3g........... 3/4 2-7 3/4.2.4 QUADRANT POWER TI LT....................................... - 3/ 4 2 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 SYSTEM INSTRUMENTATION Safety Features Actuation System......................... 3/4 3-9 Steam and Feedwater Rupture Control System............... 3/4 3-23 Antici patory Reactor Trip System.......................... 3/4 3-30a - 3/4.3.3 MONITORING INSTRUMENTATION Radi ation Monitori ng Instrumentation.........'............. 3/4 3-31 Incore Detectors......................................... 3/4'3-35 Seismic-Instrumentation.................................. 3/4 3-37 fleteorological Instrumentation........................... 3/4 3 Remote Shutdown Instrumentation.......................... 3/4 3-43 Post-Accident Moni toring Ins trumentation................. 3/4 3-46 Fire Detection Instrumentation..........-................. 3/4 3-52 Waste Gas System Oxygen-Monitor...........................-3/4 3-57 l ,- [ 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION' Startup and Power 0peration.............................. 3/4 4 Shutdown and Hot Standby................................. 3/4 4-2 3/4. 4,2 SAFETY VALVES - SHUTD0WN................................. 3/4 4-3 3/4.4.3 SAFETY VALVES AND PILOT OPERATED RELIEF VALVE'- 0PERATING.............................................. 3/4 4. DAVIS-BESSE, UNIT 1-IV Amendment No. 38,86.JM J35,797,170 -

4 e INDEX ADMINISTRATIVE CONTROLS 1 1 SECTION PAGE i i 6.1 RESPONSIBILITY................................................ 6-1

6. 2 ORGANIZATION Of f si te e.nd Ons i te Organiza tions.........................

6-1 l 4 F a c i l i ty S t a f f........................................... 6 - l a facility Staff 0vertime.................................. 6-4a l

6. 3 FAC IL ITY STAFF QUAL IF IC AT IONS.................................

6-5 6.4 TRAINING......................................................6-5

6. 5 REVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD F u n c t i o n.................................................

6-5 Comp o s i t i o n.............................................. 6 - 6 4 Al t e r n a t e s............................................... 6-6 Meeting Frequency........................................ 6-6 Quorum................................................... 6-6 "esponsibilities......................................... 6-6 A u t h o r i ty................................................ 6 - 8 l Records.................................................. 6-8 6.5.2 COMPANY NUCLEAR REVIEW BOARD F u n c t i o n................................................. 6-8 C an p o s i t i o n.............................................. 6-9 Al t e r n a t e s............................................... 6 - 9 Consultants.............................................. 6-9 DAVIS-BESSE, UNIT 1 XV Amendment No. 38,135

i L f 1: I INDEX i -ADMINISTRATIVE CONTROLS l SECTION PAGE l I Mee t i ng F req u ency......................................... 6-9 l Quorum................................................... 6-9 R e v i ew................................................... 6 - 1 0 t Au d i t s................................................... 6 - 1 1 Authority................................................ 6-12 Records..................................................6-12 6.5.3 Technical Review and Control............................. 6-12 6.6 REPORTABLE EVENT ACTI0N....................................... 6-12a

6. 7 SAFETY LIMIT VIOLATION........................................

6-13 i i.

6. 8 PROCEDURES AND PR0 GRAMS........................................

6-13 l l i 6.9 REPORTING REQUll'MENTS I i 6.9.1 Routine Reports.......................................... 6-14c I i 6.9.2 Special. Reports.......................................... 6-18 5 i 6.10 RECORD RETENTION............................................. 6-18 l t , 6.11 RADIATION PROTECTION PR0 GRAM................................. 6-20 1 !. 6.12 -HIGH RADIATION AREA.......................................... 6-20 i + }i e i: ba 6.13 E NV I RONME NTAL QU AL I F I C AT I ON................... 6-21 l' 6.14 P ROCESS ' CO NT ROL PROG RAM ( PCP )................................. 6-22 6.15 0FFSITE DOSE CALCULATION MANUAL (0DCM)....................... 6-22 i DAVIS-BESSE. UNIT 1 XVI Amendment No. 38.J?.5 a70 t

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i, : INDEX ADMINISTRATIVE CONTROLS SECTION PAGE M o e t i ng F r eq u e n cy........................................ 6-9 Q u o r um................................................... 6 - 9 Review................................................... 6-10 Audits................................................... 6-11 Au t h o r i ty................................................ 6-12 Records..................................................6-12 6.5.3 Technical Review and Control............................. 6 I

6. 6 REPORTABLE EVENT ACTI0N.......................................

6-12a

6. 7 S AF ET Y L I MI T V I OL AT I ON........................................ 6-13 5

6.8 PROC EDURES AN D PR0GR AMS....................................... 6-13 6.9 REPORTING REQUIREMENTS 6.9.1 Routine Reports.......................................... 6-14c l 6.9.2 Special Reports.......................................... 6-18 _6.10 RECORD RETENTION............................................. 6-18 l i. 6.11 RAD I ATION PROTECT IO N PR0G RAM..................................= 6-20 !!6.12 HIGH RADIATION AREA.......................................... 6-20 i!'1 ii I. 6.13 ENVIRONMENTAL QUALIFICATION.................................. 6-21 1 6.14 P ROC E S S CO NT RO L P ROGRAM ( P C P )................................ 6-22 6.15 0FFSITE DOSE CALCUL ATION MANUAL (0DCM)....................... 6-22 DAVIS-BESSE, UNIT 1 XV! Amendment No. 38, M d70

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY................................................ 6-1

6. 2 ORGANIZATION Offsite and Onsite Organizations.........................

6-1 l F a c i l i ty S ta f f........................................... 6-l a Fac il i ty S ta f f 0vertime.................................. 6-4a l

6. 3 FAC IL ITY STAFF QUAL I FIC ATIONS.................................

6-5 6.4 TRAINING...................................................... 6-5

6. 5 REVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD Function.................................................6-5 C om p o s i t i o n..............................................

6-6 Al t e r n a t e s.............................................. 6-6 Me et i ng F requ e n cy........................................ 6-6 Quorum................................................... 6-6 Responsibilities......................................... 6-6 A u t h o r i ty................................................ 6 - 8 l R e c o r d s.................................................. 6-8 6.5.2 COMPANY NUCLEAR REVIEW BOARD Function................................................. 6-8 C om p o s i t i o n.............................................. 6-9 Alternates............................................... 6-9. Consultants.............................................. 6-9 DAVIS-BESSE, UNIT 1 XV Amendment No. 38,135 l 1

INSTRUMENTATION WASTE GAS SYSTEM OXYGEN MONITOR LIMITING CONDITION FOR OPERATION 3.3.3.9 The Waste Gas System Oxygen monitor shall be OPERABLE with its alarm setpoints set to ensure that the limits of Specification 3.11.2 are not exceeded. APPLICABILITY: During additions to the waste gas surge tank. l ACTION: a. With the waste gas system oxygen monitor alarm setpoint less conservative than required by the above Specifications, declare the channel inoperable and comply with ACTION b. b. With the waste gas system oxygen monitor inoperable, additions to the waste gas surge tank may continue-provided another method for ascertaining oxygen concentrations, such as grab sample anslysis, is implemented to provide measurements at least once per four (4) hours during degassing and daily during cther operations. Exert a best efforts to return the waste gas system oxygen monitor-to' OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inopera-bility was not corrected in a timely manner. c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3.9 The waste gas system oxygen monitor shall be demonstrated OPERABLE by: a. Performance of a CHANNEL CHECK at least once per 24 hours during additions to the waste gas-surge tank. b. At least once per 92 days by performance of a CHANNEL CALIBRATION. The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal: 1. One volume percent oxygen, balance nitrogen; and 2. Four volume percent oxygen, balance nitrogen. DAVIS-BESSE, UNIT 1 3/4 3-57 Amendment No. 86,170

L l RADIDACTIVE-EFFLUENTS LIQUID HOLDUP TANKS

• LIMITING CONDITION FOR OPERATION 3.11.l_ The_ quantity of radioactive material contained in each of the j

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

gases, a.-

Outside temporary - tank. APPLICABIL. At all times. ACTION: a. With the quantity of radioactive material in any of_the above listed tanks exceeding the above limit, intnediately suspend all additions of radioactive material ~ to the_ tank and within 48 hours reduce the tank contents to within the limit, and describe the event _ leading to this condition in the next Semiannual Radio-active Effluent Release Report. b. The provisions of Specifications-3,0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS .4.11.1 The quantity of radioactive material contained in each'of the { 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._

• 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 radwaste treatment system. DAVIS-BESSE, UNIT'l 3/4.11 Amendment No. 86,170 = _ _

RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE (Hydrogen rich systems not designed to withstand a hydrogen explosion) LIMITING CONDITION FOR OPERATION 3.11.2 The concentration of oxygen in the waste gas system shall be g limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume. APPLICABILITY: 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 hours. b. With the concentration of oxygen in the waste gas system greater than 4% by volume and the hydrogen concentra' tion greater than 4% by volume, imediately 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 3re not applicable. l, SURVEILLANCE REQUIREMENTS 4.11.2 The concentrations of oxygen in the weste gas system shall be l determined to be within the above limits by monitoring the waste gases in th.e waste gas system as required by Specification 3.3.3.9. DAVIS-BESSE, UNIT 1 3/4 11-2 Amendment No. S$. 170

5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area is shown on Figure 5.1-1. LOW POPULATION ZONE 5.1. 2 The low population zone is shown on Figure 5.1-2. SITE BOUNDARY 5.1. 3 The UNRESTRICTED AREA and SITE BOUNDARY for radioactive liquid effluents is shown on Figure S.1-3. The UNRESTRICTED AREA and SITE BOUNDARY for radio-active gaseous effluents is shown on Figure 5.1-4. 5.2 CONTAINMENT CONFIGURATION 5.2.1 The containment structure is comprised of a steel containment vessel, having the shape of a right circular cylinder with a hemispherical = dome and ellipisodal bottom, surrounded by a reinforced concrete shield building. 5.2.1.1 CONTAINMENT VESSEL a. Nominal inside diameter = 130 feet. b. Nominal inside height = 285.5 feet. 0 c. Net free volume = 2.834 x 10 cubic feet, d. Nominal thickness of vessel walls - 1 1/2 inches, e. Nominal thickness of vessel dome - 13/16 inches. f. Nominal thickness of vessel bottom - 1 1/2 inches. 5.2.1.2 SHIELD BUILDING a. Minimum annular space = 4.5 feet. b. Annulus nominal volume = - 678,700 cubic feet.- c. Nominal outside height (measured from_ top of foundation base to the top of the dome) = 279.5 feet, d. Nominal inside diameter = 139.25 feet. e. Cylinder wall-minimum thickness = 2.5 feet. f. Dome minimum thickness = 2.0 feet. g. Dome inside radius = 125.29 feet, DAVIS-BESSE, UNIT 1 5-1 Amendment No.170

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ADMINISTRATIVE CONTROLS 6.8.4 (Continued) c. Post-Accident Sampling A program which will ensure the capability to obtain and analyse reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The progr'am shall include the following: (i) Training of personnel, (ii) Procedures for sampling and analysis, (iii) Provisions for maintenance of sampling and analysis equipment. d. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effl0ents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements: 1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM. 2) Limitations on the concertrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2, 3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance wi'th 10 CFR 20.106 and with the methodology and parameters in the ODCM. 4) Limitations on the annual and quarterly doses or dose comit-ment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5) Determination of cumulative and projected dose contributions from radioactive e,ffluents for the current calendar quarter and current calendar year in acenrdance.with the methodology and parameters in the ODCM at least every 31 days, DAVIS-BESSE, UNIT 1 6-14a Amendment No. 37,84,93,170

~ ADMINISTRATIVE CONTROLS 6.8.4 (Continued) d. Radioactivo Effluent Controls Program (Continued) 6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radio-activity when the projected doses in a 31-day period would-exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, 7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20 Appendix

3. Table II, Column 1, 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas-beyond the SITE B0UNDARY conforming-to Appendix I to-10 CFR Part 50, 10) Limitations on the annual dose or dose connitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190. e. Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall-provide (1) repre-sentative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following: 1) Monitoring, sampling, analysis,.and reporting of radiation and radionuclides in the environment in accordance with the method-ology and parameters in the ODCM, 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifica-tions to the monitoring program are made if required by the results of this census, and DAVIS-BESSE - UNIT 1 6 14b Amendment No.170

., = t ADMINISTRATIVE CONTROLS 6.8.4 (Continued) e. Radiological Environmental Monitoring Program (Continued) 3) Participation _in an Interlaboratory Comparison Program to'- ensure.that independent-checks on the precision and accuracy. of the measurements-of radioactive materials in environmental sample matrices are performed as ~part of the quality assurance program for environmental monitoring. 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting _ requiEements of Title 10, Code of -Federal Regulations,' the following. reports shall be submitted to the appropriate-Regional Office unless otherwise _noted. STARTUP REPORT 6.9.1.1 - A summary report of. plant startup and power escalation testing shall be submitted follow'ng (1) receipt of.an operating license. (2) amendment to _the license involving a planned increase in power level, (3) installation of fuel'that_has a different desi ~ manufactured by a different fuel supplier, and (4)gn of has b'een - modifications that may have significantly_ altered the nuclear, thermal, or hydraulic performance of the plant. 6.9.1.2: The report shall address each of the tests identified in the.- FSAR and1shall include-a description of the measured values of:the operating conditions or_ characteristics obtained-during the test program and a comparison of these values with desian predictions.and specifica-tions. Any corrective actions that were_ required to obtain satisfactory operation'shall-also be described.-. Any additional specific details-required in license conditions based on other comitments shall be - included in this report. 6.9.1.3 Startup reports _shall be submitted within-(1) 90 days following-completion of_.the startup test program, (2)_90 days following resumption or commencement-of commercial power operation, or-(3)'9 months following initial criticality, whichever is. earliest. LIf the Startup Report does-not cover all three events -(i.e... initial criticality, completion of startup test program, and resumption or comencement-of commercial DAVIS-BESSE, UNIT.I 6-14c AmendmentNo.-84,p,170-

ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission in accordance with 10 CFR 50.4 within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specifications: a. ECCS Actuation, Specifications 3.5.2 and 3.5.3. b. Inoperable Seismic Monitoring Instrumentation, Specification.3.3.3.3. c. Inoperable Meteorological fionitoring Instrumentation. Specification ?.3.3.4. d. Seismic event analysis, Specification 4.3.3.3.2. e. Fire Detection Instrumentation, Specification 3.3.3.8 f. Fire Suppression Systems, Specifica'tions 3.7'.9.1 ar 3.7.9.2. ( 6.10 RECORD RETENTION -l 6.10.1 The following records shall be retained for at least five years: a. Records and logs of facility operation covering time interval at each power level, b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of-equipment related to nuclear safety. c. All REPORTABLE EVENTS. d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications. e. Records of changes made to Operating Procedures. f. Records of radioactive shipments. g. -Records of. sealed source and fission detector leak tests and results. h. Records of annual physical inventory of all sealed source material of record. DAVIS-BESSE, UNIT 1 6-18 Amendment No. 9,J2,65,S$,J06.J25,170

I ADMINISTRATIVE CONTROLS 6.10.2 The following records shall be retained for the duration of the Facility Operating License: Records and _ drawing changes reflecting facility design modifica-- a. tions made to systems and equipment _ described in the Final Safety l --Analysis Report. ) b. Records of new and irradiated fuel inventory, fuel transfers and - assembly burnup histories.- Records of radiation exposure for all individuals entering radiation c. control areas 4 d. Records of gaseous and liquid radioactive material released to the environs. Records of transient of operational cycles for those facility e. components identified in Table 5.7-1_. f. Records of reactor tests ard experiments, l 9 Records of training and qualification for current members of the plant staff. h. Records of in-service inspections performed pursuant to these Technical' Specifications, i. Records of Quality Assurance activities required by the QA Manual. j. Records of reviews performed-for changes made to' procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.. Records of' meetings of_ the SRB and the CNRB.

i

1. _ Records for Enviror. mental Qualification which are covered under the provisions of paragraph 6.13.

Records of analyses required by the radiologicaluenvironmental' 1 m. monitoring program that would permit evaluation of the accuracy of the analyses at a later date. -This should-include procedures i effective at specified timeszand QA records showing that these procedures were followed. q Records of the service lives ofiali safety related hydraulic and

o. -

mechanical-snubbers including the date at'which the' service life 'j commences and associated installation:and maintenance records, p. Records of_ reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM. q -DAVIS-BESSE, UNIT l - 6-19 Amendment No. 8,12,86M,170-Order.-dated Oct. 24. 1980 1}}