ML20118B551

Amend 174 to License NPF-03,revising TS by Removing Fire Protection Program,Sections 3/4.3.3,fire Detection instrumentation,3/4.7.9,fire Suppression Sys & Bases & 3/4.7.10

ML20118B551
Person / Time
Site:	Davis Besse
Issue date:	09/22/1992
From:	Hopkins J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20118B552	List: ML20118B551 ML20118B554
References
NUDOCS 9210050076
Download: ML20118B551 (22)

Text

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UNITED $TATES

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THE CLEVELAND ELECTRE _lllVMINATlf1G COMPANY DONET No. 50-345 DAVIS-BESSE flVCLEAR P()WER STATION. UNii NO,1 AMEND 11[ffT TO FACILilY OPERATING LICENSE Amendment flo. Fi4 License 110. NPF-3 1.

The lluclear Regulatory Coumission (the Commission) has found that:

A.

The application for anendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland Electric illuminating Company (the licensees) dated November 1, 1991 as supplemented December 26, 1991, and June 1, 1992 cocplies 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 t' Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can l'e conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance wi'h the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the lechnical Specifit ations as indicated in the attachment to this license amendment, and by amending paragraphs 2.C.(2)(a) and 2.C.(4) of facility Operating License No, f1PF-3 to read as follows:

'/210050076 920922 PDR ADOCK 0S000346 p

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i (a) Technical Specifications i

The Technical Specifications contained in Appendix A, as revised through Amendment No.174, are hereby incorporated in the license.

The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

2.C(4)

Toledo Edison shall implement and maintain in effect all provisions of the approved fire ProtectJon Program as described in the Updated Safety Analysis Report and ti approved in the SERs dated July 26, 1979, and May 30, 1991, subject to the following provicions:

Toledo Edison may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

3.

This license amendment is effective as of its date of issuance and shall i

be implemented not later than 90 days after issuance.

4 FOR THE NUCLEAR REGULATORY COMMISSION

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/ on B. Hopkins, Sr. Project Manager Project Directorate 111-3 Division of Reactor Projects lil/IV/V Office of Nuclear Reactor Regulation Attachments: 1. Amended page 8 to License No. NPF-3

2. Changes to-the Technical Specifications Date of issuance: September 22, 1992 e

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ATT ACHMFJT TO LICENSE AMENDMENT NO.17't FAClllTY OPERATING tlCENSE NO. Npfd

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DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

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

The corresponding overleaf pages are also provided to maintain document completeness.

1 Remove Insert Index IV Index IV Index Vil Index Vli

- i Index X11 Index XII i

3/4 3-51 3/4.3-51 3/4 3-52 through 3/4 3-56 3/4 7-37 through 3/4 7-48 3/4 7-37 8 3/4 3-3 B 3/4 3-3 B 3/4 7-6 8 3/4 7-6 6-la 6-la i

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2.C.(4) Fire Protection Toledo Edison shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Updated Safety Analysis Report and as approved in the SERs dated July 26,1979, and May 30, 1991, subject to the following provision:

Toledo Edison may make changes to the approved Fire Protection Program without prior approval of the Commission only if thM changes would.

not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire, j

2.C.(5) Toledo Edison Company shall maintain in effect and implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation.

The program shall include:

(a)

Identification of a sampling schedule for the critical parameters and control points for these parameters; i

(b)

Identification of the procedures used to quantify parameters that are critical to control, points;-

(c)

Identification of process sampling points; (d)

Procedure for the recording and management of data; (e)

Procedures defining corrective actions for off control point chemistry conditions; and (f) A procedure identifying the authority responsible for the interpreta-tion of the data, and the sequence and timing of administrative events required to initiate corrective action.

2.C.(6) Antitrust Condition _s Centerior Service Company shall comply with the antitrust conditions delineated in Condition 2.E of this license as if ntmed therein.

Toledo Edison Company is responsible and accountable for.the actions of Centerior Service Company to.the extent that Centerior Service Company's actions contravene the antitrust license conditions of Condition 2.E of this license.

2. 0 The licensee shall fully implement and maintain in effect all. provisions-of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to.

the authority of 10 CFR 50.90 and 10 CFR-50.54(p).

The plans, which-contain Safeguards Information protected under 10_CFR 73.21, are entitled:

" Davis-Besse Nuclear Power Station Physical Security Plan,"

with revisions submitted through January 29, 1988; " Davis-Besse Nuclear Power Station Guard Training and Qualification Plan," with revisions submitted through. February 20, 1987; and " Davis-Besse Nuclear _ Power...

Station Safeguards: Contingency Plan," with revisions submitted-through-February 20, 1987.. Changes made in accordance with 10 CFR 73.55 shall be implemented in 'accordance with the schedule set forth therein.

. Amendment No. 152,174 a.,

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INDEX LIMITING _ CONDITIONS FOR OPERATION AND SURVEILLANCE.__ REQUIREMENTS SECTION PAGE 3/4.0 AP PL I C AB I L I T Y.............................................

3/ 4 0- 1 3/4.1. REACTIVITY CONTROL SYSTEMS 3.4.1.1 BORATION CONTROL 1

Shutdown Margin........................................

3/4 1-1 Boron Dilution.........................................

3/4 1-3 t

Moderator Temperature Coefficient.......................

3/4 1-4 Minimum Temperature for Critica10....................... 3/4 1-S_

3/4.1.2 BORATION SYSTEMS Flow Paths - Shutdown..................................

3/4 1-6 Flow Paths - Operating.................................

3/4 1-7 Ma k eu p Pump - Shu tdown.................................. 3/ 4 1 - 9 Ma k eup Pumps - Opera ti ng...............................

3/4 1-10

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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 1

Borated Water. Sources - Operating.....................

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

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

3/4 1-21 Position Indica tor Channels............................. - 3/4 1-22 Rod Drop Time..........................................

3/4 1-24 Sa fety Rod Ins ertion L imi t.............................

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

3/4 1-26 Rod Frogram............................................

3/4 1-30 o

Xenon Reactivity.......................................

3/4 1 '

Axial Power Shaping Rod Insertion Limits-...............

3/4-1 :

1 1

DAVIS-BESSE, UNIT L 111-Amendment No. 38 o

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INDEX LIMITIN3 CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 A X 1 AL POW E R I MB AL AN C E....................................

3/ 4 2-1 3/4.2.2 NUCLEAR HEAT FLUX HOT CHANNEL FACTOR - F................

3/4 2-5 0

4 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - FhH...........

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

3/4 2-9 3/4.2.5 DNB PARAMETERS...........................................

3/4 2-13

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3/4. 3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENT ATION................

2/4 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 Anticipatory Reactor Trip System.........................

3/4 3-30a 3/4.3.3 MONITORING INSTRUMENTATION Radi a tion Moni toring Instrumentation.....................

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

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

3/4 3-37 lieteorologi cal Ins trumentation...........................

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

3/4 3-43 Post-Accident Monitoring Instrumentation.

3/4 3-46 Deleted l

Waste Gas System Oxygen Monitor..........................

3/4 3-57 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power 0peration..............................

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

3/4 4-2 3/4.4.2 S AF ET Y V ALVE S - S HUT D0WN.................................

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

0 P E RAT I N G..............................................

3 / 4 4 - 4 DAVIS-BESSE. UNIT 1 IV Amendment No. 3E,26,J34.J35,)97, J/PJ74

P INDEX LIMITING CONDIT10kS FOR OPERATION AND SURVEILLAf1CE REQUIREMENTS L

SECTI0ff PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Va1ves..............................................

3/4 7-1 Auxil ia ry f eedwa t e r Sys t em.................................

3/ 4 7-4 Condens a t e S tora g e T a nk s...................................

3/ 4 7-6 l

A c t i v i ty...................................................

3/ 4 7 - 7 Main Steam Line Isolation Va1ves...........................

3/4 7-9 Motor Driven feedwater Pump System.........................

3/4 7-12a 3/4.7.2 STE AM GENERATOR PRESSURE / TEMPERATURE L IMIT ATION............

3/4 7-13 3/4.7.3 COMPONENT C00Ll!4G l'.TER SYSTEM.............................

3/4 7-14 3/4.7.4 S E RV I C E WAT E R SY ST EM......................................

3/ 4 7-15 3/4.7.5 U L T I M AT E H E AT S I N K.........................................

3/ 4 7 - 1 6 3/4.7.6 C0!4 TROL ROOM EMERGENCY VENTIL ATION SYSTEM..................

3/4 7-17 3/4.7.7 SNUBBERS...................................................

3/4 7-20 3/4.7.8 SEALED SOURCE CONTAMINATION................................

3/4 7-36 3/4.7.9 Deleted 3/4./.10 Deleted 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0 p e r a t i n g..................................................

3/ 4 8 - 1 S h u t d ow n...................................................

3 / 4 8 - 5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A. C. Di s tri bution - Opera ti ng..............................

3/4 8-6 A. C. Di st ri but i on - Shu tdown...............................

3/4 8-7 D. C. Di s tribu tion - Opera ti ng..............................

3/4 B-8 D.C. Distribution -

Shutdown.......................

3/4 8-11 DAVIS-BESSE UNIT 1 Vil AmendmentNo.?E,J03,J05,J35,)ff,174

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INDEX

. LIMITING, CONDITIONS FGR OPERATION AND SURVE LL NCE REQUIREMENTS I

A SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BO RON CONCE NT R AT ION.....................................

3/ 4 9-1 3/4.9.2 INSTRUMENTATION..........................................

3/4 9-2 3/4.9.3 D E C AY T I M E...............................................

3 / 4 9 - 3 3/4.9.4 CONT AIMME NT P EN ET RAT I ONS.................................

3 / 4 9-4 3/4.9.5 CO MM U N I C AT I O N S...........................................

3 / 4 9 - 5 3/4.9.6 FUEL HANDLING BRIDGE OPERABillTY........................

3/4 9-6 3/4.9.7 CRANE T RAVEL - FUEL HANDLING BUILDING...................

3/4 9-7 3/4.9.8 DECAY HEAT REMOVAL AND COOLANT CIRCULATION All Water Levels.............................

3/4 9-8 Low Water Level.........................................

3/4 9-8a 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM.......

3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL....

3/4 9-10 3/4.9.11 STORAGE P00L WATER LEVEL.................................

3/4 9-11 3/4.9.12 STORAGE POOL VENTILfT10N...............................

3/4 9-12 3/4.9.13 SPENT FUEL POOL FUEL ASSEMBLY ST0 RAGE....................

3/4 9-13

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3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DI ST RI BUT I ON L I M I T S....................................

3/ 4 10- 1 3/4.10.2 P H Y S I C S T E ST S............................................

3/ 4 10- 2 3/4.10.3 RE ACT O R COOL ANT L 00P S....................................

3/ 4 10- 3 3/4.10.4 SHUT DOWN MARGIN...........

3/4 10-4 DAVIS-BESSE, UNIT 1 Vill Amendment No. 2P,130 l

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i INDEX BASES SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS T

3/4.6.1 PRIMARY CONTAINMENT.........

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS........

B 3/4 6-2 3/4.6.3 CONTAINMENT ISOLATION VALVES............

B 3/4 6-3 l

B 3/4 6-4 3/l. 6.4 COMBUSTIBLE CAS CONTROL..

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3/4.6.5 SHIELD BUILDING,...

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INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE...................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION B 3/4 7-4 3/4.7.3 COMPONENT COOLING VATER SYSTEM.

B 3/4 7-4 3/4.7.4 SERVICE VATER SYSTEM.

B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK.

B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SY3 TEM.

B-3/4 7-4 3/4.7.7 SNUBBERS.

B 3/4 7-5 3/4.7.8 SEALED SOURCE CONTAMINATION............

B 3/4 7-6 3/4.7.9 Deleted 3/4.7.10 Deleted 3/4.8 ELECTRICAL POVER SYSTEMS.

B 3/4 B-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.

B 3/4 9-1 3/4.9.2 INSTRUMENTATION.

B 3/4 9-1 3/4.9.3 DECAY TIME.....................

B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS.

B 3/4 9-1 3/4.9.5 COMMUNICATIONS.

B 3/4 9-1 DAVIS-PESSE, UNIT 1 XII Amendment No./35,1W,% 5.174

Pages 3/4 3-51 through 3/4 3-56 deleted.

Next page is 3/4 3-57.

DAVIS-BESSE, UNIT 1 3/4 3-51 Amendment 9,34,135,174 i

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[LANT SYSTEMS SUR\\11LIANCE_ REQUIREMENTS (Continued) 1.

Vith a half-life greater than 30 days (excluding Hydrogen

3) and 2.

In any form other than gas.

b.

Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous six months.

Scaled sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use.

Startup sources and fission detectors - Each sealed startup c.

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

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

P DAVIS-BESSE, UNIT 1 3/4 7-37

i 3/4.3 INS 1RUMENTATION BASES REM 0'" SHUTOOWN INSTRUMENTATION (Continued)

HOT STANDBY of the facility fran locations outside of the control room.

This capability is required in the event control room habitability is lost.

3/4.3.3.6 POST-ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the post-accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

The containment Hydrogen Analyzers, although they are considered part of the plant post-accident monitoring instrumentation, have their OPERABILITY requirements located in Specification 3/4.6.4.1, Hydrogen Analyzers.

3/4.3.3.7 CHLORINE DETECTION SYSTEMS - Deleted 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION Deleted l

JAVIS-BESSE, UNIT 1 B 3/4 3-3 Amendment No. 9,ED,EB)34, Jbf,lhi,174

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_3/4.7.8 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.

This limitation will ensure that leakage from by-product, source, and special nuclear material sources will not exceed allowable intake values.

3/ 4. 7. 9 FIRE SUPPRES$10N SYSTEMS -- DELETED i

3/4.7.10 FIRE BARRIERS -- DELETED f

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i DAVIS-BESSE, UNIT 1 B 3/4 7-6 Amendment No. 9,JEE,J3E.174 -

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I 6.0 ADMINISTRATIVE CONTROLS 6.2.2 FACILITY STAFF a.

Each on duty shift shall be composed of at least the minimum shif t crew composition shown in Table 6.2-1.

b.

At least one licensed Ope >ator shall be in the control panel area when fuel is in the reactor, c.

At least two licensed Operators, one of which has a Senior Reactor Operator license, shall be present in the control room while in MODES 1, 2, 3, or 4.

d.

An individual qualified in radiatirl protection procedures shall be on site when fuel is in the reactor #.

e.

All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to fuel Handling who has no other concurrent responsi-bilities during this operation.

f.

Orleted g.

The Manager-Plant Operations shall either hold or have held a senior reactor operator's license on a pressurized water reactor.

The Operations Superintendent shall hold a senior reactor operator license for the Davis-Besse Nuclear power Station.

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1. The individual qualified in radiation protection procedures may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in ordcr to accommodate unexpected absence, provided immediate action is -taken to fill the required position.

DAVIS-BESSE, UNIT 1 6-la Amendment No. 7,JE,9E,JJE,J35,J37 (next page is 6-2) 144, 174

ADji!NISTRATIVE CONTROLS

6. 3 FACILITY STAFF QUAllFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the 'ianager - Radiological Control who shall meet or Axceed the qualifications of Regulatory Guide 1.8, September 1975..(2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in.a scientific or engineering discipline with specific training in plant = design, and response and analysis of the plant for transients and accidents, and (3) the Manager - Plant Operations whose requirement for a senior reactor i

operator license is as stated in Specification 6.2.2 9

6. 4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Manager - Nuclear Training and-shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and of 10 CFR 55.59.

6.4.2 Deleted 6.5 REVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD (SRB)

FUNCTION 6.5.1.1 The Station Review Board (SRB) shall function to advise the Plant Manager on all matters related to nuclear safety.

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

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ADMINISTRATIVE CONTROLS COMPOSITION 4

6.5.1.2 The Station Review Board (SRB) shall be composed of at least six members of the Davis-Besse onsite management organization.

The members shall-be as a minimum, managers or individuals reporting directly to managers from i

each of the following disciplines:

plant operations, maintenance, planning, radiological controls, engineering, and quality assurance.

The members shall meet the requirements of ANSI N18.1-1971, Sections 4.2, 4.1, or 4.6 for applicable required experience.

The SRB Chairman shall be drawn from the SRB members and designated'in writing by the Plant Manager.

ALTERNATES

6. 5.1. 3 All alternate members shall be appointed in writing by the SRB Chairman; however, no more than two alternates shall participate as voting members in SRB-activities at any one time.

MEETING FREQUENCY 4

6.5.1.4 The SRB shall meet at least once per calendar month and as convened by the SRB Chairman or his designee.

QUORUM

6. 5.1. 5 A quorum of the SRB shall consist of the Chairman or his desinnee and four members including alternates.

RESPONSIBIL 1_T_l ES 6.5.1.6 The Station Review Board shall be responsible for:

a.

Review of plant administrative procedures and changes thereto, b.

Review of the safety evaluation for 1) procedures, 2) cnanges to procedures, equipment or systems, and 3) tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions do not constitute an unreviewed safety question.

c.

Review of proposed procedures and changes to procedures and equipment determined to involve an unreviewed safety question-as defined in 10 CFR 50.59.

DAVIS-BESSE, UNIT 1 6-6 Amendment No. 12,76,98,JO9,J3E,137, 142, 169

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ADMINISTRATIVE CONTROLS d.

Review of proposed tests or experiments determined to involve an unreviewed safety question as defined in 10 CFR 50.59.

e.

Review of reports of violations of codes, regulations, orders, Technical Specifications, or Operating License requirements having nuclear safety significance or reports of abnonnal degradation of systems designed to contain radioactive material.

f.

Review of all proposed changes to the Technical Specifications or the Operating License.

g.

Deleted h.

Review of reports of significant operating abnormalities or devi-ations from normal and expected performance of plant equipment that affect plant safety.

l i.

Review of the Industrial Security Plan, the Security Training and Qualification Plan, and the Security Contingency Plan, and changes thereto.

j.

Review of the Davis-Besse Emergency Plan and changes thereto.

L Review of items which may constitute potential nuclear safety hazards as identified during review of facility operations.

1.

Investigations or analyses of special subjects as requested by the Company Nuclear Review Board.

l m.

Review of all REPORTABLE EVENTS.

Review of all Safety Limit Violation Reports (Section 6.7).

n.

o.

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 Plant Manager and to the CNRB.

p.

Review of the changes to the OFFSITE DOSE CALCULATION MANUAL.

1 Review of the changes to the PROCESS CONTROL PROGRAM.

r.

Review of the Annual Radiological Environmental Operating Report.

s.

Review of the Semiannual Radioactive Effluent Release Report.

T.

Review of the Fire Protection Program and changes thereto.

l DAVIS-BESSE, UNIT 1 6-7 Amendment No. 27,M,93,9E,MP, Abh/,174

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ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The Station Review Board shall a.

Recommend to the Plant Manager written approval or disapproval of itees considered under Sections 6.5.1.6 a, e, d. f 1 and j.

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b.

Render determinations in writing with reFard to whether or not cach item considered under Sections 6.5.1.6 a, c, d and f above constitutes an unreviewed safety question as defined in 10 CFR 50.59.

t c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice l

President, Nuclear and the Company Nuclear Review Board of disagreement between the SRB and the Plant Manageri.however, the Plant Manager shall have responsthflity for resolution of such disagreenents pursuant to 6.1.1 above.

d.

Make recommendations in writing to the Plant Manager that actions reviewed under Section 6.5.1.6 b above do not constitute an unreviewed safety question.

RECORDS 6.5.1.8 The Station Review Board shall maintain written ninutes of each meeting and copfes shall be provided to the Plant'Hanager, Vice President, l

Nuclear and Chairman of the Company Nuclear Review Board.

6.5.2 COMPANY Fl' CLEAR RFVIEW BOARD (CNRB)

FUNCTION 6.5.2.1 The Company Nucleer Review Peard (CNRP) shall function to provide independent review and audit of designated activities in the areas of:

a.

Nuclear power plant eperations, b.

Nuclear engineering, c.

Chemistry and radiochemistry, d.

Metallurgy, e.

Instrumentation and control, f.

P.adiological safety, g.

Mechanical and electrical engineering end h.

Quality assurance practices.

. DAVIS-BESSE, trNIT 1 6-8 Amendment No. 27,Ff,pt.109

c 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.

Inoperable Meteorological fionitoring Instrumentation, Specification c.

3.3.3.4.

d.

Seismic event analysis, Specification 4.3.3.3.2.

e.

Deleted f.

Deleted 6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

Records and logs of facility operation covering time interval a.

at each power level b.

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

All REPORTABLE EVENTS.

d.

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

e.

Pecords 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 sc.

material of record.

5 DAVIS-BESSE, UNIT 1 6-18 Amendment No. 9,J7,f 5,EE,J06,J35gl60174

6 ADMINISTRATIVE CONTROLS 6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a.

Records and drawing changes reflecting facility design modifica-tions made to systems and equipment described in the Final Safety Analysis Report.

b.

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

c.

Records of radiation exposure for all individuals entering radiation control areas, d.

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

e.

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

f.

Records of reactor tests and experiments, g.

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

h.

Records of in-service inspections performed 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.

1.

Records for Environmental Qualification which ;re covered under the' provisions of paragraph 6.13.

m.

Records of analyses required by the radiological environmental monitoring program that would permit evaluation of the accuracy of the analyses at a later date.

This should include procedures effective at specified times and QA records showing that these procedures were followed.

o.

Records of the service li~ves of all safety related hydraulic and mechanical snubbers including the date-at which _the service life commences and associated installation and maintenance records,

p. : Records of reviews performed for changes made to the 0FFSITE DOSE CALCULATION HANUAL and the PROCESS CONTROL PROGRAM.

DAVIS-BESSE, UNIT 1 6-19 Amendment No. E,12.Bf.9/.170 Order dated Oct. 24.c1980

-,