ML19341C716
| ML19341C716 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/04/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19341C715 | List: |
| References | |
| NUDOCS 8103040002 | |
| Download: ML19341C716 (30) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
/,. E WASHINGTON. D. C. 20555 g /-
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a DAIRYLAND POWER COOPERATIVE DOCKET NO. 50-409 LA CROSSE BOILING WATER REACTOR AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 23 License No. DRP-45 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Dairyland Power Cooperative (the licensee) dated August 6,1980, as supplemented September 16, 1980 and November 18, 1980, complies witn 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; 8.
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 endange. ring the health and safety.of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;
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D.
The issuance of this amendment will cot 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 satisfi::d.
8.10804000 %
2.
Accordingly, the license is amended by changes to the Technical Specificatiosn as indicated in the attachment to this license amendment and paragraph 2.C(2) of Provisional Operating License No. DPR-45 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A issued October 31, 1969, with Authorization No. DPRA-6, as revised through Amendment No. 23, are hereby incorporated in the 11c<.nse. The licensce shall operate the facility in accordance with the Technical Speci fi cations.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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-h W.
Den'nTs"M. Crutch fi el d, C ef Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Speci fications Date of Issuance: February 4,1981 S
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ATTACHMENT TO LICENSE AMENDMENT NO. 23 LA CROSSE BOILING WATER REACTOR (LACBWR) 1 PROVISIONAL OPERATING LICENSE NO. DPR-45 Revise Appendix A by replacing the following pages with the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT Contents i (Table of Contents) ij*
23-27u(1)23-27t (Intentionally Blank) 27u 27rr 27rr 28 28 42 42**
]
6 6-19 (last portion of J
Appendix A)
N a
a
- Also reflects environmental qualification provisions issued by Order i
dated October 24, 1980.
- This page is included to reinstate Section 5.2.6 which was inadver-tently omitted during the issuance of the Appendix A for DPRA-6, October 31, 1969.
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TABLE OF CONTENTS Page 1.
SITE..............................
1 1.1 LOCATION 1
1.2 EXCLUSION AND RESTRICTED AREAS 1
1.3 PRINCIPAL ACTIVITIES 1
2.
DESIGN AND PERFORMANCE REQUIREMENTS 1
2.1 REACTOR BUILDING 1
- 2.2 REACTOR VESSEL 3
2. 3' FORCED CIRCULATION SYSTEM.................
4 2.4 REACTOR AUXILIARY SYSTEMS.................
6 2.5 MAIN STEAM AND FEEDWATER LOOP......
11
)
2.6 ELECTRICAL POWER SUPPLY.......
12 I
2.7 REACTOR CORE AND VESSEL INTERNALS.....
13 2.8 CONTROL R0D DRIVE SYSTEM 16 2.9 CONTROL SYSTEMS..............
17 2.10 SAFETY AND MONITORING SYSTEMS...............
18 2.11 WASTE DISPOSAL 21 2.12 FUEL STORAGE AND HANDLING.........
22 3.
ADMINISTRATIVE AND PROCEDURAL SAFEGUARDS
( Deleted) l i
4 OPERATING LIMITATIONS 26 4.1 GENERAL..........................
26 4.2 OPERATIONS LIMITS.............
28 l
5.
MAINTENANCE 37 5.1 GENERAL 37 I
5.2 TESTING..................
39 5.3 INSERVICE INSPECTION PROGRAM 53 4
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Change No. #,
L Amendment No. 23
TABLE OF CONTENTS (Cont'd)
Page 6.0 ADMINISTRATIVE CONTROLS.................
6-0 6.1 - RESPONSIBILITY,
6-0 6.2 ORGANIZATION...
6-0 6.3 UNIT STAFF QUALIFICATIONS 6-5 6.4 TRAINING.....
6-5 6.5 REVIEW AND AUDIT......................
6-5 6.6 REPORTABLE OCCURRENCE ACTION.......
6-11 6.7 SAFETY LIMIT VIOLATION 6-11 6.8 PROCEDURES.........................
6-11 6.9 REPORTING REQUIREMENTS...................
6-12 6.10 RECORD RETENTION.
6-17 6.11 RADI ATION PROTECTION PROGRAM......
6-18 6.12 HIGH RADIATION AREA 6-18 6.13 ENVIRONMENTAL QUALIFICATION 6-19 e
1 1
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a j
ii Amendment No. 23
3.0 ADMINISTRATIVE CONTROLS (INTENTIONALLY BLANK)
S ChangeNo.M Amendmen t No. 4, 8. JF, 2 3 (Pages23-27t)
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4.0 OPERATING LIMITATIONS 4.0.1 DEFINITIONS For purposes of the Safety Limits and Limiting Safety Systems Settings, Section 4.n.2;' Reactor Coolant Activity, Specification 4.2.2.22; Elec-trical Power Systems, Section 4.2.3; and the Power Distribution Limits.
Section 4.2.4.2. Technical Specifications only, the following ter=s are defined and appear in capitalized type so that uniform interpretation may be achieved.
A* TION ACION shall be. those additional requirements specified as' corollary statements to each principal specification and shall be part of the specifications.
AVE? AGE PLANAR EXPOSURE The AVEPAGE PLANAR EXPOSURE shall be applicable to a specific planar heicht and is equal to the sum of the exposure of all the fuel rods in the specified bundle at the specified height divided by the nur.ber of fuel rods in the fuel bundle.
AVEP/.GE PLAf!AR LINEAR HEAT GENERATION RATE The AVERAr,E PLANAR LINEAR HEAT r,ENERATION RATE (APLHGR) shall be applicable to a specific planar heigh t and is ecual to the orm nf the LINEAR HEAT GE*...' TION PATES for all the fuel rods in the specified A
bundle at the specified height Svided by the number of fuel rods in tha fuel -bundie.
D**D *D'Tl o M S.
m oo 27u Amendment No. /, 23 i
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-27rr-i (THIS PAGE IS BLANK INTENTIONALLY)
Celeted 4.1.1 4.1. 2 i
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Amendment No. W,23 l
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'4.1 GENERAL 4, or During periods when the reactor is in Condition 3, I
5, either Channel 1 or 2 of the Nuclear Instrumentation
^
4.1.3 System shall be in operation and shall be monitored by the operator.
4.1.4 Whenever the reactor contains one or more fuel elements, any
. operations from points outside the con:rol room of equipment which may affect the reac:or shall be condue:ed under the direction, cr with the knowledge, of the control rcom operator.
4.1.5 If the plan is operational during a tornado warning, the shift supervisor on duty shall keep informed of the actual tornado activity which may approach the plant, in the even: :na: reports indicate an 4-inent tornado strike at or near the LAC 3WR plant, the shif: superriser shall reduce reactor power to a level which per=1:s prompr redue:1on of power generation to statica load.
However, the shif: supervisor shall i
be instrue:ed to discontinue plant opera: ion if, in his judgment, this action is required to ensure plant safety.
4.1.6 A progra= for the periodic inspec:ica of pri:nry system components will be developed and implemented by the end of the first year of
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operation.
4.2 OPERATIONS !.IV.ITS 4.2.1 Reacter Building 4.2.1.1 Con:ain=ent vessel in:egrity sha'l be =ain:ainsd; all access
- o and egress from the reac:cr building shall be c:nfined to :he air locks; and all syste=s for autoca:ically closing penetrations shrril be in operating condition, or the penetrations shall be isola:ed whenever:
(a) there is fuel in the reacter, and the reac:or coolant tenparature i
exceeds 250%,
(b) irradiated fuel is being handled, (c) :here is fuel in the reactor, and any centrol rod is. withdrawn, I
(d) :here is fuel in the reze:or, and cain:enance is being performed on :he pri=ary systa=.
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(c) Corrective Action: Valve malfunctions disclosed by any Type C test shall be corrected and reported in a subsequent technical report.
(see'section 5.2.1.5 below.)
Leaks which exceed the acceptance criteria of (b) shall be repaired and retested until the criteria are met.
Repairs of lesser leaks are optional.
(d) Test Frequency:
Type C tests shall be performed during each reactor shutdown for major refueling, but in no case at intervals greater than 1 year.
- 5. 2.1.4 Permissible Periods for Testing: The performance of Type A tests shall be limited to periods when the plant facility is nonoperational and secured in the shutdown condition under administrative control and safety procedures.
J 5. 2.1. 5 Report of Test Results: The leakage rate results of Type A, B, and C tests that meet the acceptance criteria shall be reported in the applicable LACBWR operating report.
Leakage test results of Type A, B, and C tests that fail to meet the acceptance criteria shall be reported in a separate summary that includes an analysis and interpretation of the test data, the least-squares fit analysis of the test data, the instrumentation error analysis, and the structural conditions of the con-tainment or components, if any, which contributed to the failure in meeting the acceptance criteria.
Results and analyses of the supplemental verification test employed to demonstrate the validity of the leakage rate test measurements also shall be included.
5.2.2 The reactor building isoletion system will be tested for proper operation prior to every cold startup, but this test will not be required more often than at 30-day intervals.
5.2.3 The exterior surfaces of the LACBWR ventilation stack and the smoke stack of the conventional steam power generating station, Genoa 3, adjacent to the LACBWR plant shall be inspected for structural integrity at an interval no longer than 5 yr following the initial construction
. inspection, and at subsequent ir ;e*vals not longer than 5 yr apart.
5.2.4 The reactor vessel shall be hydrostatically tested at 1400 psig aftgr any of its gasketed joints have been opened and resealed. All hydrostatic tasts shall be performed with the vessel at a temperature no lower than that specified in Sec. 4.2.2.4.
S r2.5 The forced circulation system controls and automatically-operated valves shall be tested for proper operation annually.
5.2.6 The shutdown condenser system control valves shall be tested at least quarterly to demonstrate their operability.
The integrated system shall be tested for proper operation annually.
In addition, the condenser tube bundle shall be pressurized to greater than 1250 psig and tested for leakage annually.
5.2.7 The high-pressure core spray system controls and remotely-operated valves shall be tested semi-annually to demonstrate their operability.
The integrated system shall be tested for proper operation annually.
This annual test shall include a determination of the differential pressure between the coolant supply line and the reactor vessel.
Change No. EI, }d Amendment No. 23,
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6.0 ADMINISTRATIVE CONTROLS l
6.1 RESPONSIBILITY 6.1.1 The Plant Superintendent shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibi,lity during his '
absence.
6.1.2 The Shift Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control-Room command function.
A management directive to this effect, signed by the (highest level of corporate management) shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support' shall be as shown on Figure 6.2.1-1.
UNIT STAFF 6.2.2 The unit organization shall be as shown on Figure 6.2.2-1 and:
a.
Each on duty shift shall be cceposed of at least the oinimum shift crew composition shown in Table 6.2.2-1.
b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
c.
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation 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 Reac~ tor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
LACBWR 6-0 Amendment No. )<r,23
I f.
A Fire Brigade of at least 5 membe'rs shall be maintained on site at I
all times." The Fire Brigade shall not include the two LACBWR Plant Operators necessary for safe shutdown of the unit or any other j,
personnel required for other essential functions during a fire i
emergency.
i<.
g.
At all times. when the reactor is critical, or when its controls are being manipulatef with fuel in the reactor, the control room shall be attended by a minimum of two persons, one of whom shall have a valid Operators License and shall have full responsibility for operation of the facility.
6.2.3 SHIFT TECHNICAL ADVISOR The Shift Technical Advisor shall serve in an advisory capacity to the Shif t Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.
fire Brigade rompo.ition may be less than the minimum requirements for a
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period of t ime not to exceed ? hours in order to arrommodat e unexpect ed ah.cnce of f ire Driunde member *. provided imniediat e act ion 1. taken to re-
!. tore the fire Hrlyade to within the minimum requirements.
This provision does not permit any Ilre Brigade position to be unmanned upon shift change due to an oncoming Brigade member being late or absent.
-LACBWR 6-1 Amendment No. KI, 23
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s tr: a>- Amendment No. M,23 1.ACBWR i oo m g g l 1_. oc o ,.2 i
[ GENIRAl ii4 NAGER SAFETY REVIEW l' ~ COMMITTEE { E g' ASST. GENERAL MAtlAGER l N PO4ER l TECil. SUPPORT LACBWR OPERAfl0NS CONTRACTORS PLANT SUPERINTENDENT REVIEW COMMITTEE I I ~ RAD. PROILCIION ON-SiTL TECliNICAL I I QUALITY ASSURANCE ASSI. PLANT SUPT. STEN 0GRAPilERS SUPERVISOR SECURITY MANAGER (SOL) ~ ENGINEER SUPPORT ] REACl0R ENGINEER l NUCLEAR triGlktLH -1 OA SPECIALIST l HEALIli & SAFETY PROCESS ENGINEER INSTRUMENT ENGINtLR' SUPERVISOR ELECTRICAL ENGINEER 1 OPERATIONS ENGINEER J -i OA TECHNICIANS I HEALIH PilYSICS MFCHANICAL ENG NEER** cn TECHNICIANS TECH. SUP. ENf NEER O I SECURITY DIRECTOR l TECH SUP ENGINEER TECH. SUP, ENGINEER ASST. MECH. ENGINEER ENGINEERING ASSIST, E I i = h', MAINTENANCE 11ECHANICAL OPERATIONS SUPERVISOR (SOL) INSTRUMENT & ELECTRICAL SUPERVISOR
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SUPERVISOR z I INSTRUMENT MECHANICAL SHIFT ASSISTANT TO TECHNICIANS MAINTENANCE SUPERVISORS (SOL) OPERATIONS SUPERVISOR I & TRAINIM (50L) ---LE LEC T R I CI ANS ] PLANT OPERATORS (OLJ ro RELIEF SUPERVISOR NOTE:
- Instrument Engineer and I&E FIRE PROTECTION (SOL)
Supervisor positions may be held by same person. DAIRYLAND POWER COOPERATIVE
- Responsible for Fire LACBWR FACILITY ORGANIZATION Protection Program FIGURE 6.2.2-1
Table 6.2.2-1 MINIMUM SHIFT CREW COMPOSITION # POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION Conditions 1, 2, 3 Condition 4 Condttion 5 55 1 1 1 SRO None None 1 R0 1 1 1 A0 2 1 1 STA 1 None None SS Shift Supervisor with a Senior Reactor Operator's License SRO Individual with a Senior Reactor Operator License or a Senior Reactor Operator Limited to Fuel Handling that is supervising core alterations R3 Individual with a Reactor Operator's License Auxiliary Operator A3 STA Shift Technical Advisor Except for the Shift Supervisor and the Reactor Operator, tt shift crew composition may be one less than the minimum requirer .s of Table 6.2.2-1 for a period of time not to exceed two hours , order to accommodate unexpected absence of on-duty shift crew members pro- } vided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.2-1. This provision , does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent. bring any absence of the Shift Supervisor from the control room while i he unit is in condition 1, 2, 3, 4, or 5, an individual (other than t the Shift Technical Advisor) with a valid R0 license shall be designated to assume the control room command function, ishift crew composition may be less than the minimum requirements for a period of time n,t to exceed 2 hours in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum j requirements of Table 6.2.2-1. l 6-4 Amendment No. ,23 [ l i
ADMI ISTRATIVE CONTROLS \\ 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meeh or exceed the minimum qualifi-cations of ANSI N18.1-1971 for comparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. 6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommenda~tions of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55. 6.4.2 A training program for the Fire Brigades shall be maintained under the direction of the Operations Engineer cnd shall meet the requirements of Section 27 of the NFPA Code-1975, except for the frequency of Fire Brigade training sessions, which shall be held at least once per 92 days. f _6.5 REVIEW AND AUDIT
- 6. 5.1 OPERATIONS REVIEW COMMITTEE (ORC) f FUNCTION f. 5.1 The Operations Review Committee shall function to advise the Plant i
Superintendent on all matters related to nuclear safety, COMPOSITIO_N i l . 6. 5.1.2 The Operations Review Committee shall be composed of'the: l Chairman: Plant Superintendent i ~ Members : Operations Supervisor Operations Engineer Mechanical Maintenance Supervisor Instrument Engineer Instrument and Electrical Supervisor Reactor Engineer Health and Safety Supervisor Nuclear Engineer Assistant Superintendent Process Engineer Staff Engineers Mechanical Engineer Shift Supervisors Assistant Mechanical Engineer Training & Relief Supervisor Technical Support Engineer Radiat-ion Protection Engineer RTERNATES f 6.5.1.3 All alternate members shall be appointed in writing by the ORC Chairman ; to serve on a temporary basis; however, no more than two alternates shall participate as voting members in ORC activities at any one time. 6-5 Amendment No. J, 23 LACBWR
ADMI.NISTRATIVE CONTROLS MEETING FREQUENCY
- 6. 5.1. 4 The ORC shall meet aEleast once per' calendar month and as convened by the ORC Chairman or his designated alternate.
QUORUM 6.5.1.5 The minimum quorum of the ORC necessary for the performance of the ORC responsibiilty and authority provisions of the Technical Spe'cifications shall consist of the Chairman, or his designated alternate, and four members, including alternates. RESPONSIBILITIES
- 6. 5.1. 6 The Operations Rev.iew Committee shall be responsible for:
a. Review of (1) all procedures required by specification 6.8 and changes thereto, (2) any other proposed procedures or changes thereto as determin-d bv the Plant Superintendent to affect nuclear safety. b. Review proposed tests and experirents that affect nuclear i sa fety. Review of all proposed changes to the Appendix "A" Technical 5,pecifi-g c. cations. I l d. Review of all proposed changes or codificatiorts to unit systems or equipment that affect nuclear safety, f e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Assistanct General Manager-Power Group and to the Safety Review Committee (SRC). f. Review vf events requiring 24-hour written notification to the Ccmmission, g. Review of unit operations to detect potential nuclear. safety hazards. h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Plant Superintendent or SRC. i. Review of the Plant Security Plan and irnementing procedures and shall submit recommended changes to the SRC. l s j. Review of the Emergency Plan and implementing procedures and shall ) submit recommended changes to the SRC. l I i t i I l GCBWR 6-6 Amendment No. 14, 23 6 3
"AbMINISTRATIVE CONTROLL -. AtJTHORITY* 6.5.1.7 The Operations Review Col =sittee shall: a. Recommend in writing ;c the Plant Superintendent approval or. dis- + approval of items considered under 6.5.1.6a through.d above. b. Render determinations in writing with regard to whether or not each ites considered under 6.5.1.6a through e above constitutes an unreviewed safety question. ' "- " c. Pre' vide written notification within 24 hours to the Assistant Gener'al Manager-Power Group and the SRC of disagreement between the CRC and the Plant Superiritandent; however, the Plant Superintendent shall have responsibility for resolution of such disa eements pursuant to 6.1.1 above. ~ 1 RECORDS
- 6. 5.1. 8 The Operations Review Con =ittee shall maintain ten minutes of each ORC meeting that, at a ninimum, document the result all ORC activities performed under the responsibility and authority provisi
- f these Technical Scecifications. Copies shall be provided to the Assistz eneral Manager-Power Group and the SRC.
6.5.2 SAFETY REVIEV COWITTEE (SRC) PJNCTION
- 6. 5. 2.1 The SAFETY REVIEW COMMITTEE shall function to pr,ide independent review and audit of designated activities in the areas of:
a. Nuclear power plant operations. b. Nuclear engineering, c. Chemistry and radiochemistry, d. Metallurgy, e. Instrumentation and control, o f. Radiological safety, g. Mechanical and electrical engineering, and h. Quality assurance practices. LACEWR 6-7 Amendment No. )T,23
ADMINISTRATIVE CONTROLS-.. u COMPOSITION 6.5.2.2 The SRC shall be composed of the: Chairman: Consultant Members: Consultant Plant Superintendent Dairyland Power Cooperative (DPC) Environmental Department Manager Assistant General Manager-Power Group ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Ch' airman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time. CONSULTANTS 6.5.2.4 Consultants shall be utilized as deter =ined by the SRC Chairman to ~ provide expert advice to the SRC. l MEETING FREQUENCY l 6.5.2.5 The SRC shall meet at least once per six months. l OUDRUM l 6.5.2.6 The minimum quorum of the SRC necessary for the performance of the r SRC review and audit functions of these Technical Specifications shall consist of the Chairman, or his designated alternate, and at least 3 SRC members, including alternates. No core than a minority of the quorum shall have line responsibility for operation of the unio. \\ REVIEW 6.5.2.7 The Safety Review Committee shall review; a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provisions of Section 50.59, 10 CFR, to verify that such actions did not consti-tute an unreviewed safety question. j i b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR. I LAC 5WR 6-8 Amendment No. )l, 23
ADMINISTRATIVE CONTR0i.S REVIEW (Continued) c. Proposed tests or Experiments which involve an unreviewed safety - question as defined in Section 50.59, 10 CFR. d. Proposed changes to Appendix "A" Technical Specifications er this Operating License. e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of intarnal procedures or instructions having nuclear safety significance.. f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear salecy. g. Events requiring 24 hour written notification to the Commission. h. All recogni:ed indications of an unaaticipated deficiency in same aspect of design or operation of safety related structures, systecs, or components that could affect nuclear safety. i. Reports and meeting minutes rf the Operations Review Committee. AUDITS 6.5.2.8 Audits of unit activities shall be perfor=ed under the cogni:ance of the SRC. These audits shall encompass: a. The confor=ance of unit operation to provisions contained within the Appendix "A" Technical Specifications and acplicable license conditions at least once per 12 months. ~ b. The performance, training and qualifications of the entire unit staff at least once per 12 months. c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that i affect nuclear safety at least once per 6 months. d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months. e. The Emergency Plan and icolementing procedures at least once per 24 months. LACSWR 6-9 Amendment No. 7, 23
E .AbMINISTRATIVECONTROLS AUDITS (C'antinued) f. The Security Plan and implementing procedures at least once per 2,4 months. g. The Fire Protection Program and implementing procedures at least once per 24 months. h. An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utill:ing either qualified offsite Itcensee personnel or an outside fire protection firm. 1. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at i least once per 36 months. j. Any other area of unit operation considered appropriate by the SRC or the DPC General Manager. AUTHORITY 1 6.5.2.9 The SRC shall report to and advise the DPC General Manager on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8. RECORDS 6.5.2.10 Records of SRC activities shall be prepared, approved and distributed as indicated below: [ a. Minutes of each SRC eteting shall be prepared, approved and forwarded to the OPC General Manager within 20 days following each meeting. Reports of reviews ence= passed by Sec$ ion 6.5.2.7 above, shall be b. prepared, approved and forwarded to the DPC General Manager within 20 days following cocpletion of the review. c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded; to the DPC General Manager and to the management positions responsible' for the areas audited within 30 days after completion of the audit. a i EI [ !: LACSWR 6-10 Amendment No. /I,23 i 1 -I D**'
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O
AD$INISTRATIVECONTROLS' 6.5 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES: a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9. b. Each REPORTABLE OCCURRENCE requiring 24 hour notification to the Commission shall be reviewec' by the CRC and submitted to the SRC and the Assistant General Manager-Power Group. 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: a. The unit shall be placed in at least HOT SHUTDOWN within two hours. b. The NRC Operations Center shall be notified as soon as possible and in all cases within one heur. The Assistant General Manager - Power Group and the SRC shall be notified within 24 hours, c. A Safety Limit Violatien Report shall be prepared. The report shall be reviewed by the ORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems or structures, and (3) corrective action taken to prevent recurrence. d. The Safety Limit Violation Report shall be submitted to the Co= mission, the SRC and the Assistant General Manager-Power Group within 14 days of the violation. S.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained , covering the activities referenced below; a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978. b. Refueling operations. c. Surveillance and test activities of safety related equipment. t, i i LACBWR 6-11 Amendment No.jf, 23
ADMINI$TRATIVE CONTROLS. PROCEDURE 5*(Continued) 1 d. Security Plan implementation. e. Emergency Plan implementation. f. Fire Protection Program Implementation. 6.8.2" Each procedure of 6.8."1 above,' and changes thereto, shall be reviewed by the ORC and approved by the Plant Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures. 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided: a. The intent of the original procedure is not altered. ~ b. The change is approved by two members of the unit management staff, l at least one of whom holcs a Senior Reactor Operator's License on the unit affected. c. The change is docu=ented, reviewed by the ORC and approved by the Plant Superintendent within 14 days of implementation. 6.9 REPORTING REQUIREMENTS .f ROUTINE REPORTS AND REPORTABLE OCCURRENCES l 6.9.1 In addition to the a::plicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement, unless otherwise noted. i STARTUP REPORT ,6. 9.1.1 A summary report of plant startup and p:wer escalation testing shall ce submitted following (1) receipt of an operatin,g license. (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manuf actured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, Lhermal, or hydraulic performance of the unit. a I [ t t 0 ? O b 1 66 63.S.E f Amendment No. /, 23 LACBWR 6-12
' ADMIAISTRATIVE CONTROLS _.. --. STARTUP REPORT (Continued) 6.9.1.2 The startup report shall address each of the tests identified in the Safeguards Report for Operating Authorization as required for the test program being conducted and shall include a description of the measured values of the operating conditions or enaracteristles obtained during the test program and a comparison of these values with design predictions and specifications. 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 commitments shall be included in this report. 6.9.1.3 Startup reports shall be submitted within (1) 90 days followin3 completion of the startup test program, (2) 90 days following resumption or l commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events, i.e., initial criticality, completion of startup test program, and resumption or comencement of comercial power operation, supplementary reports shall be submitted at least every three months until all three events have been completed. I l ANNUAL OPERATING REPORT _
- 6. 9.1. 4 Annual reports covering the operation of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each The initial report shall be submitted prior to March I of the year year.
following initial criticality. 6.9.1.5 Reports required on an annual basis shall include: l A tabulation on an annual basis of the number ?.f station, utility and a. other personnel, including contractors, receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions,l/ e.g., reactor
- operations and surveillance.
inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. l In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions. l/ This tabulation supplements the requirements of Section 20.407 of 10 CFR Part 20. 6-13 Amendment No. g, 23 LAC'BWR
4 ADMINISTRATIVE CONTROLS f 3 MONTHLY OPERATING REPORT ~ 6.9.1.6 koutine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Comission, Washington 0.C. 20555,. with a copy to the Regional Office of Inspection and Enforcement, to arrive no - later than the 15th of each month following the calendar month covered by the report. REPORTABLE OCCURRENCES 6.9.1.7 The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of ccrrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date. PROMPT NOTIFICATION WITH GITTEN FOLLOWUP 6.9.1.8 The types of events listed below shall be reported within 24 hours by telephone and confirmed by telegraph, mailgram, or facsimile transmissi~on to the Director of the Regional Office, or his designate no later than the first working day following the event, with a written followuo rcport within two weeks. The written followu;, report shall include, as a minimum, a completed copy of a licensee event report form. Infomation provided on t.he licensee event report form shall be supplemented, as needed, by accitional narrative material to provide complete explanation of tne circumstances surrouncing the event. Failure of the reactor protection system or other systems subject to t. limiting safety system settings to initiate the -required protective function by the time a monitored parameter reacnes the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function. b. Operation of the unit or affected systems when any parameter or j operation subject to a limiting condition for operation. is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specificaticns, Abnormal degradation discovered in fuel cladding, reactor coolant c. piessure boundary, or primary containment. i LAC 3WR 6-14 Amendment No. ff, 23
A'DMINISTRATIVE CONTROLS PROMPT NOTIFICATION WITH VRITTEN FOLLOWUP (Cantinued) d. Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power' operation greater than or equal to 1lll celta k/k; a calculated reactivity balance indicating a SHUTDCWN MARGEN less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if suberitical, an unplanned reactivity insertion of more than 0.5lli, delta k/k; or occurrence of any unplanned criticality. e. Failure or malfunction of one or more ecmponents which preve-ts or could prevent, by itself, the fulfillment of the functional :equire-ments of system (s) used to cope with accidents analyzed in the-Safeguards Report for Operating Authori:ation. f. Personnel error or procedural inacequacy which prevents or could I prevent, cy itself, the fulfill:ent of the functional requirements of systems required to cope with accicants analy:ed in the Safeguards Report for Operating Authorization g. Conditions' arising from natural or r.an-made events that, as 'a direct result of the event require plant shutdown, cperation of safety systems, or other protective measu es required by technical specifi-cations. h. ' Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have pemitted reactor operation in a manner less conse vative tnan assumed in the analyses. i. Performance of structures, systems, or components that recuires e remedial action or corrective measures to prevent operation in a manner less conservative than assamec in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the exist-ence or development of an unsafe condition. THIRTY OAY WRITTEN REPORTS 6.9.1.9 The types of events listed below shall be the subject of written reports to the Of rector of the Regional Office within thirty days of occurrence of the event. The written report shall include, as a minimum, a con 61eted copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional n3rrative material to provide complete explanation of the circumstances surrounding the event. LACBVR 6-15 Amendment No, I, 23
ADMIk!STRATIVE CONTROLS - - THIRTY DAY WRITTEN REPORTS (Continued) Reactor protection system or engineered safety feature instrument l a. settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems. b. Conditions leading to operation in a degraded mode perm'itted 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 or engineered safety i. f 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. SPECIAL REPORTS 6.9.2 Special reports 'shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. l I 6.9.3 Unique Reporting Requirements a. Semi Annual Effluent Release Report a I Paragraph (a)(2) of Part 50.36a, " Technical Specifications on Effluents from Nuclear Power Reactors," of 10 CFR Part 50 requires that a report be made to the Cermission within 60 days after January 1 and July 1 of each year. The report shall specify the quantity of each of the principal radionuclides released to unrestricted areas by liquids and gaseous effluents during the previous 6 months of operation. The information submitted shall be in accordance with Regulatory Guide 1.21 ~ (Revision 1) dated June 1974 and Regulatory Guide 4.1 dated January 18, ! 1973. o i t I LACBWR 6-16 Amendment No.4,f, 23
ADMINISTRATIVE CONTROLS 6.10 RECdRD RETENTION--- In addition to the applicable retord retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated. 6.10.1 The following records shall be retained for at least fi've years,: a. Records and logs of facility operation covering tis.e inttrval at each power level. b. Records and logs of principal maintenance activities, itapections. ' repair and replacement of principal itees of equipment related to nuclear safety. c. All REPORTABLE OCCURRENCES submitted to the Commission. d. Records of surveillance activities, inspections and calibrations required t. these Technical Specifications. a. Records of changes made to the procedures required by Specjf fcation 6.8.1. f. Records of radioactive shipments. I g. Records of sealed source and fission detector leak tests and results. I h. Records of annual physical inventory of all sealed source material of record. 6.1.0. 2 The following records shall be retained for the duration of the LACBWR f Operating License: 3 Records and drawing changes reflecting' facility design modifications a. made to systems and equipment described in the Safeguards Report for Operating Authori:ation. i b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories. 1 Records of radiation exposere for all individuals entering radiation c. control areas. d. Records of gaseous and licuid radioactive material released to the i environs. i i i i l LAC 3WR 6-17 Amendment No.,}6,23 l ~ i 1
ADMINISTRATIVE CONTROLS j 4 RECORD RETENTION (Continued) Records of transient or operational cycles for those facility compo-e. nents identified in Table 5.7.1-1. f. Records of reactor tests and experiments. i g. Records of training and qualification for current members of the / unit staff. j h. Records of in-service inspections perfor=ed pursuant to these Technical Specifications. j i. Records of Quality Assurance activities required by the Operatio~nal Quality Assurance Manual. Records of reviews performed for changes made to procedures or l ~ f. equipment or reviews of tests and experiments pursuant to 10 CFR 50.59. k. Records of meetings of the ORC and the SRC. 1. Records of environmental qualification which are covered under the Provisions of Section 6.13. 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. 6.12 HIGH RADIATION AREA I i 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which trie intensity of ' radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).* Any individual or group of individuals permitted to enter su:n areas shall be provided with or accompanied by one or more of the following: ' health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas. Change No. M, g LACBWR 6-18 Amendment No. 23 i J
~~ ADMINISTRATIVE CONTR0tS HIGH RADIATION AREA (Continued) A radiation monitoring device which continuously indicates the a. radiation dose rate in the area. b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is recalved. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been estab-lished and personnel have been made kncwledgeable of them. An individual qualified in radiation protection procedures who is c. equipped with a radiation dose rate monitoring device. This indi-vidual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the unit Health Physicist in the Special Work Permit. 6.12.2 The requirements of 6.12.1, above, shall also apply to each high racia-tion area in which the intensity of radiation is greater than 1000 mrem 7hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be caintained under the acministrative control of the Shift Supervisor on duty and/or the' unit Health Physicist. E.13 ENVIRONMENTAL QUALIFICATION
- s A.
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 "Gudielines for Evaluating Environmental Qualification of Class IE Electrical 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 Modification of License DPR-45 Dated October 24, 1980. B. By no later than December 1,1980, complete and audit ble records must be available and maintair.ed at a central location which describe the environmental qualificatio.n method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the D0R Guidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified. Amendment No. g 23 6-19 t;tgwg f.h Order dated 10/24/80 Of? D C D MI} P N d ud g}}