ML20215L675
| ML20215L675 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/22/1986 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20215L662 | List: |
| References | |
| TAC-M63189, NUDOCS 8610290241 | |
| Download: ML20215L675 (22) | |
Text
{{#Wiki_filter:. _ 6.0 A:" NISTEAT .'E CONTRCLS 6.1 RESPONSIBILITY
%gr 6.1.1 The $ Plant kp:r ntendent) shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibi-lity during his absence.
6.2 CPG 412ATIC4 0FFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1. FACILITY STAFF
- 6. ;t- I ad 6.2.2 TheFacilityorganizationshallbeasshownonFiguref.2-2and:
- a. Each on duty shift shall be composed of at least the minimum-shift crew composition shown in Table 6.2-1.
- b. At least one licensed erator shall be in the control room when fuel is in the reacto I
- c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reacter 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 Reactor Operator Limited to Fuel Handling who has no other concurrent respon-sibilities during this operation.
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**f. A site Fire Brigade of at least 5 members shall be maintained onsite at all times #. The Fire Brigade shall not include 3 members of the minimum Shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.
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\ pyd;gJ.nlsoI;l.<Jjn rJ*iim Proleshm P ntre irrig~ade Composition may be less than the minimum requirements for a period of time not to exceed 2 hours in order to accomodate unexpected absencejef fir; Pi; d: -M:- provided immediate action is taken tov
- ter: th: " : ?r';9 te eithi- tM 9'm m&: rte. h/84 /TMM
^^This d.nse free te 5 individueli ,,ill te bpi;.;;nted by stort up i +fter the first r;fuelin; ;t;;:.
6-1 Amendment flo. p, 18 DAVIS-BESSE. UNIT 1 g l 8610290241 861022 l PDR ADOCK 05000346 I P PDR
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DAVIS-5 ESSE. UNIT 1 6-3 ' AMENDMENT NO. 2,76
Tills PAGE PROVIDED FORINFORETION ONLY TABL. 6.2-1 MINIMUM SHIFT :REW COMPOSITIONf LICENSE APPLICA8LE MODES EMRY 1,2,344 546 50L 1 1 OL 2 1 Non-Licensed 2 1 Shift Technical Advison 1 None Required
*Does not include the licensed Senior Reactor Operator or Santor Reactor Operator Limited to Fuel Handling supervising CORE ALTEPATIONS.
# Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours in order to accomodate unexpected absence of on duty shift crew members provided imediate action is taken
' to restore the shift crew composition to within the minimum requirements of Table 6.2-1. DAVIS-8E55E. UNIT 1 6-4 Amendment flo. 37
ASSISTANT PLANT MANAGER OPERATIONS I OPERATIONS SUPERINTENDENT I OPERATIONS SHIFT TECHNICAL E N ER SUPERVISOR ADVISOR SUPERVISOR SUPERVISOR SHIFT SUPERVISOR ASSISTANT SHIFT SUPERVISOR REACTOR OPERATOR EQUIPMENT AND AUXILIARY OPERATOR DAVIS-BESSE NUCLEAR POWER STATION OPERATIONS ORGANIZATION FIGURE 6.6-2 DAVIS-BESSE, UNIT 1 6-3
6.0 ADNINISTRATIVE CONTROLS
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.( -
- FACIt,ITY STAFF OVERTIME i -
6.2.3 Administrative precedures shall be developed and taplemented te limit the werktag hours of facility staff who perfesa safety-related fumatiosa; e.g., seater roaster operaters, reacter . operators, health physisists, auxiliary operaters, and key asistemasse pereennel. i Adequate shift severage shall be asiststand without routtaa ! heavy use of evertime. The objective shall be to have operattag perseasel verk a nerasi 8-hour day. 40-hear week while the plant, is operattag. Bowever le the event that unforeseen problems require substantial anos..a of evertime to be used. er durias i estended pertede of shutdous for refueltas asjer asisteessas er major plaat modifiestions, en a temporary basis, the following ll guidelines shall be felleved:
- a. As individual should set be permitted to work more than 16 -
hours straight, ensluding shift turnover time. -
- b. An individual should not be petuitted to work more than 16 hours is any 24-hour period, aer more than 24 hours in any
! 48-hour period, nor more than 72 heers is any seves-day period, all ensludtag shift turbevor time. I
- c. A break of at least eight hears should be allsved between
! verk periode, issluding shift turnover time. I
- d. Except during eatended shutessa partsda, the see of evertime I should be considered on an individual basis and set for the entire staff en a shift. -
i plan 4 Money.r l Any
" deviation from the above guideltase shall be aethertsed by the
;: & t d ::. his designes, or higher levels of assagement, in l accordance with established presadares and with docuasatation of the basis for graattag the deviattee. Individual everties shall be reviewed by station Managoasst to secure that ancesetve hours have set been seeigned. sentiae deviaties from the above guidelines is set authertsed.
day!S-5 ESSE UNIT 1 6-44 Amenennt No. M
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l > \ AC"!4!$TRAT!vt CONTROL 3 l 4.3 FACILITY STAM OUALIFICA710NS i 6.3.1 fach member of the facility staff shall meet er escoed the sinta m l qualifications of ANS! N14.11971 for comparatie positions, escast for (1)
.tmZn 7;;rnt= t :;; ) une shall aset er saceed the quali- l ca ions of Angulatory Guide 1.8. Septeter 1975 and (2) the Shift Tech-l j nical Adviser une shall have a bachelor's degree or equivalent in a scientific or engineering discipli.m with specific training in plant design, and response and analgis Physio of the pleet Superinhandent Gansrel for transtants and acci. l dancs. ksenisby anel Heel 6.4 TRAIN!NS 6.4.1 A retraining and replacement training program fbr the facility staff shall be maintained under the direction of the Nuclear Training m.ek - t;;- and shall meet or exceed the requirements and recommendations I of Section 5.5 of AN5! N18.1-1971 and Appendix "A" of 10 CFA Part 55.
i , 6.4.2 A training program for the Fire Origade shall be maintained under the direction of the Fire Marshall and shall meet or exceed the requirements of Section 27 of the NFPA Code-1974. 4.5 atVitV AND Aue!T 4.5.1 5TATTON ttV!!W SQMD (SRE) i t PUNC 10N l 4.5.1.1 The Station Review leard (SRB) shall function to advise'the N en all matters related to nuclear safety. i plant A najor l j i i I l l l ) . l
- Avis-assar, art 1 ss Amenemas no.X g ,sg ,
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i . ADMlhlbiRAl1VE _ColilROLS ~ .'
- ie ADDITIONAL CHANCES PREVIOUSLY COMPOSITION -
PROPOSED BY LETTER Seria!No. /235 Date /-@-F6 6.5.1.2 The Station Review Board sG11 be composed of the: Chaim.:.n: M:d :r: A::izt: t St:ti:n p;rintendent Op:rs tica: Enghwter Med:r: Technical Engia cr M: der: M: int:n::: Engineee
-M:d: : le:d Instr :t :nd C: tr:1 Enc'neer Meder:
Med:r: "" clear and Perfer-ince E gineir Med:r: S=i:t and M::lth ."hy:icist
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C 6.,.n &.4. an.- - . . -. - ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the SRB Chairman to serve on a temporary basis; however, no more than two . alternates any one time. shall participate as voting members in SRS activities at
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MEETING FREQUENCY - 6.5.1.4 The SRB shall meet at least once per calendar month and as convened by the SRB Chairman or his designated alternate. QUORUM 6.5.1.5 A quorum of the' SRB shall consist of the chaidan or his designated alternate and four members including alternates. RESPONSIBILITIES 6.5.1.6 The Station Review Board shall be responsible for:
- a. Review of 11 all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as detennined by the Station Superintendent to affect nuclear safety,
- b. Review of all proposed tests and experiments that affect nuclear safety.
,,, DAVIS-BESSE, UNIT 1 6-6 Amendment No, n, 76
ADDITIONAL CHANGES PREVIOUSLY .
, a ,, : . . ; ,, . ,
,, PROPOSED BY LETTER
) ., . : Serial No. /J36 Date /-d2-b M j
. ADMINISTRATivt CONTROLS '
- c. Review of all proposed changes to Appendix "A" Technical specifications.
- d. Review of all proposed changes or modifications to plant
; systems or equipment that affect nuclear safety.
I
- e. Investigation of all violations of the Technical specificatient including preparation and forwarding of reports covering evalua-tion and recormendations to prevent recurrence to the Vi:a l
President - Nuclear and to the Chairman of the Comoany Nuclear Review Soard.
- f. Review of all REPORTA8LE EVENT 3.
- g. Review of facility operations to detect potential safety hazards.
- h. Pe'rfor-ance of soecial reviews, investigations and analyses
- and resorts thereon as reevested by the Chair =an of the l
Cascany Nuclear Review Board.
- 1. Review of the Plant Security Plan and inslerenting preced.res and shall submit recoemended changes to the Chairman of tne Company Nuclear Review Board.
J. Review of the Emergency Plan and taplementing procedures and shall submit recessended changes to the Chairman of tne Company Nuclear Review Board. 1 I k. Review of any unplanned, accidental er uncontrolled radteactive i releases, evaluation of the event, ensurance that remedia) action is identified to prevent recurrence. review of a report covering the evaluation and forwarding of the report to the Station Superintendent and to the CNRS. 1 1. Review of the OFF5ITE 00$I CALCULATION MANUAL and implementation
! of precedures at least once per 24 months.
- s. Review of the PROCESS CONTROL PROGRAM and isolamentation of precedures for processing and packaging of radioactive wastes at least once per 24 senths.
! n. Review of the Annual Radielegical Environmental Operating Report.
- e. R. view of the se.iann ai Radi tive affivent R.i.a.e R rt.
,i . DAVIS-BEsst, tat!T 1 6-7 AmendmentNo.27.N'93 l
INSERT "A" Chairman: Station Review Board Chairman
- Member: Assistant Plant Manager, Operations Member: Assistant Plant Manager, Maintenance Member: Technical Support Manager Member: Chemistry and Health Physics General Superintendent Member: Plant Operations Engineering Supervisor Member: An Engineering Director or Performance Engineering Manager Member: Operations Quality Assurance Manager Member: Plant Operations Superintendent
- Designated in writing by the Plant Manager. The Chairman will be drawn from SRB members.
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' PROPOSED BV LETTER IADMINISTRATIVE CONTROLS Serial No. /035 Date /-224
. . . .. .. a AlfiHORITY 6.5.1.7 The Station Review Board shall:
a. Recomend to the Station Superintendent written approval or disapproval above. of items considered under 6.5.1.6(a) through (d) b. Render deteminations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question. c. Provide written notification within 24 hours to thkV ce President, Nuclear and the Company Nuclear Review Board of disagreement between the SRB and the Station Superintendent; however, the Station Superintendent shall have responsibility
- for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS .
- 6. 5.1. 8 The Station Review Board shall maintain written minutes of
- each meeting and copies shall be provided to the)4 ice President. Nuclear and Chaiman of the Company Nuclear Review Board.5edor l 6.5.2 C09ANY NUCLEAR REVTFW BOARD (CNRB)
FUNCTION 6.5.2.1 The Company Nuclear Review Board (CNR8) shall function to provide 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,
- f. Radiological safety,
- g. Mechanical and electrical engineering, and
- h. Quality assurance practices.
i DAVIS-8 ESSE UNIT 1 6-8 Amendment No. 27, 86
~-
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- ADDITIONAL CHANGES PREVIOUSLY - .
PROPOSED BY LETTER ADMINISTRATIVE CO'NTROLS l COMPOSITION - 6.5.2.2 .The Company Nuclear Review Board shall be composed of the: Chairman: Director, Fossil Facilities Engineering and Construct.lon Member: General Superintendent. Transmission and Substations Members - Superintendent Davis-Besse Sr.ation Members - Director, Nuclear Services Member: Director, Quality Assurance Hember General Superintendant, Fossil Generation Facilities l Member: Director, Nuclear Safety J Member: Director, Nuclear Facility Ensinnaring Member Others as deemed advisabla by tbc cNRB Chairman
- 3 ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the CNR8 Chairman to serve on a temporary basis; however, no more than two alter-nates shall participate as voting members in ,CNR8 activities at any one time.
CONSULTANTS _
- 6. 5. 2. 4 Consultants shall be utilized as determined by the CNRB Chair..an to prov,ide expert advice to the CNRB.
E MEETING FRE0VENCY
- 6. 5. 2. 5 The CNRS shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading ar.d at least once per six months thereafter.
OUORUM 6.5.2.6 A quorum of CNRS shall consist of the Chairran or his designated alternate and at least half of the appointed CNRS meters or their alternates. No more than a minority of the cuorum shall have line responsibility for operation of the facility.
*0thers as deemed advisable by the CNRB chairman, who are appointed to the Company Nuclear Review Board shall have an academic degree in an Engineering or Physical Science Field; and in addition, shall have a minimum of five years of technical experience, of which a minimum of three years shall be in one or more of the areas specified in Specification 6.5.2.1.
DAVIS-8 ESSE, UNIT 1 6-9 Amendment No. 12, 27, 76
, . - . - , . + ---+- - -- -
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Vis L ADMIN!$TRATIVECONTRk$ FBRINFORMATION ONLY l AEVIEW . 6.5.2.7 The Campan Nuclear Review Board shall review:
- s. Thesafetyevaluationsfor1)changestoprocedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59. 10 CFR to verify that such actions did not constitute an unreviewed safety question.
- b. Proposed changes ta procedures, equipment or systems dich involve an unreviewed safety question as defined in Section 50.59. 10 CFR.
- c. Proposed tests or experiments dich involve an unreviewed safety question as defined in Section 50.59, 10 CFR. -
- d. Proposed changes in Technical Specifications or this Operating License.
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- e. Violations of codes, regulations, orders. Technical $pecifications.
Itcense requirements, or of ir. tarnal procedures or instructions having nuclear safety significance,
- f. Significant operating abnormalities or deviations from normal and expected perforssace of plant equipment that affect nuclear safety.,
9- ALL REPORTABLE EVENTS.
- h. All recognized indications of an unanticipated deficiency in some aspect of design er operation of safety related structures, systems, or components.
- 1. Reports and meetings sinutes of the Station Review Board. /
i DAV!$-BESSE. WIT 1 $=10 knendment No. 93
y . IMS PAGE PROVIDED . s- X# ADMINISTRATIVE CONTROL 5 FORINFORMATION 0NLY AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the CNRB. These audits shall encompass:
- a. The conformance of unit ' operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
- b. The performance, training and qualifications of the entire station 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 affect nuclear safety at least once per 6 months. .
- d. The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months.
- e. The Station Emergency Plan and implementing procedures at least once per 12 months.
- f. The Station Security Plan and implementing procedures at least once per 12 months.
- g. Any other area of facility operation considered appropriate by the CNRB,
- h. The Facility Fire protection Program and implementing procedures at least once per 24 months.
1 An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm. J. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per.36 months.
- k. The performance of activities required by the Quality Assurance i
Program to meet the provisions of Regulatory Guide 1.21. Revision 1 June 1974 and Regulatory Guide 4.1, Revision 1. April 1975 at least once per 12 months.
~ DAVIS-BESSE, UNIT 1 6-11 Amendment No. )(, pf, J4, 86 l
l
ADDill0NAL CHANGES PREVIOUSLY PROPOSED BY LETTER SerialNo. /J36 Date h2:24 lADMINISTRATIVECONTROLS l AUTHORITY sen;orVee.PnkdonAclw 6.5.2.9 The Company Nuclear Review Board shall report to and advise the4l specified in Sections 6.5.2.f and 6.5.2.8.7.e.ide;.; ud Chi:f 0;;r: tin- Offi :r o RECORDS
. 6.5.2.10 Records of Comeany Nu: lear Review Scard activities sr..11 he prepared, approved and distributad as indicated below:
- a. Minutas be prepared, approved and forwardedof to each CNRS the T. ids; setting
=d 0.i;f sbter 0;;r: tin; Offi;mrice presac l
and CNA8 asmoers within 14 days following each meeting.
- b. Reports of reviews encousassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the "r;;H:-t =: Chi:f l 0:: :tii; Of'he and CNRS seemers within 14 days f I owing
^
comolation of the review. senior vke Res ; noche
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- c. Audit reports encemoassed by Section 6.5.2.8 above, shall be forwarded to the ?. .;f;=t 2: Chi:10;;r; ting Offi;;r i
- and CNRS members and to the management positions responsible
. . for the areas audited within 30 days after comolation o' tne sudit. sanier nes%4h nAnlev J.5 a:rva.ae.: EVENT ACTION 6.5.1 The following actions shall be taken for APORTA!LE IVENTS: ,
a .. The Comission shall be notified and/or a recort subc:itted ,- pursuant to the requirements of SECTION 50.73 to 10 CFA ,,. PART 50, and
- b. Each REPORTABLE EVENT shall be reviewed by the SRB, and the results of this review shall be submitted to the CNRS and theVVice President, Nuclear. l
$snaOf DAVIS-BESSE, UNIT 1 6-12 Amendment No. /1, 17, 93
; 5 ADDITIONAL CHANGES PREyl0VSLY PROPOSED BY LETTER Seria! No. /235 Date /-hfG ADMINISTRATIVE CONTROLS 6.7 SArtTY LfMfT V10Laff0N 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: .
- a. The facility shall be placed in at least NOT STANOBY within one hour.
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- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the $R8. This report shall describe (1) applicable circumstances preceding the violation. (2) effects of the violation upon facility components. systems or
. structures, and (3) corrective action taken to prevent recurrence,
- d. The'$afety Limit Violation Report shall be submitted to the Comission, the CNR! and therVice President. Nuclear within l 14 days of the violation. 58aior
!.! *t0*!:"8t! A#D P&O6eAMS l 6.8.1 Written procedures shall be estabitshed, implemented and main-tained covering the activities referenced below:
- a. The acclicable procedures recommended in Appendix "A" of Regulatory Guide 1.33. November. 1972.
- b. Refueling operations.
. c. Surveillance and test activities of safety related equipment.
- d. Security Plan implementation,
- e. Emergency Plan implementation.
- f. Fire Protection Program implementation.
- g. The radiological environmental monitoring program.
- h. The Process Control Program.
- 1. Offsite Dose Calculation Manual implementation.
6.8.2 Each pmcedure of 6.8.1 above, and changes thereto, shall be reviewed by the SRB and approved by the Station Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures. DAVIS-BESSE. UNIT 1 6-13 Amendment No. 9. 12. 27,86
INSERT "B"
- b. The Safety Limit violation shall be reported to the NRC Operations Center by telephone as soon as possible and in all cases within one hour. In addition the Senior Vice President, Nuclear and the CNRB shall be notified within 24 hours.
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- Date/-pa-P6
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./llP1s!' Rt.Tivt CONTac[.5
- .i.2 Temporary changes to procedures of 6.8.1 above may be made provised: ,
- a. The intent of the original procedure is not altered.
- b. The change is approved by two members of the plant management staff, at least one of whom holds a Sector Reactar Operator's License on tas unit affected. l
- c. The change is documented, reviewed by the SRS and approved by the Station Superintendent within 14 days of implementation.' ..
6.8.4 The following prograss shall be established, ispiamented,'and maintained
- a. primary Coolant Sources Outside Containment A program to reduce leakage from those portions of system outside containment that could contain highly radioactive fluids during a serios transient or accident to as low as practical levels. The system include makeup, letdown, seal injection, seal return, low pressum injection, containment spray, hiWe pressure injection, waste gas, prienry saspling
\ and reactor coolant drain systans. The progran shall include the following:
(1) Preven'tive maintenance and/or periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less, i
- b. In-plant Radiation Monitorine A program which will ensure the capability to accurately deter-mine the airborne lodine concentration in vital areas under accident conditions. This program shall include the following:
(1) , Training of personeel, (ii) Pmcedures for monitoring, and (iii) Provisions for maintenance of saspling and analysis eouip-t I ment. DAV!5-8 ESSE, UNIT 1 6-14 Anembent ito.)()U 51
Eg . .. c ; THIS PAGE PROVIDED . u o. = .uJ FORINFORMATION ONLY ADMINISTRATIVE CON 1R01.5 6.8.4 (Cont.)
- c. Post-Accident Sampline A program which will ensure the capability to obtain and analyze reactor coolant, radioactive fodines and particulates in plant gaseous affluents, and containment atmosphere samples under accident conditions. The program shall include the following:
(1) Training of personnel, (ii) Procedures for sampling and analysis, (111) Provisions for maintenance of sampling and analysis equipment. 6.9 REPORTINA REOUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the appropriate Regional Office unless othenvise noted. STARTUP REPORT 6.9.1.1 A summary report of plant startup and rower escalation testin shall be submitted following (1) receipt of an Jperating license (2) g amendment to the Itcensee involving a planned ',ncrease in power level. (3) installation of fuel that has a different design or has been manu. factured by a different fuel supplier, and (#) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant. 6.9.1.2 The report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be in-cluded 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 ope, ration, 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 commencement of commercial DAVIS-8 ESSE, UNIT 1 6 14a Amendment No. U, % 93
- t. .
. .a ani THIS PAGE PROVIDED v cm.m 7 ..'n FORINFORMATION ONLY ADMINISTRAT"IVE CONTROLS power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
ANNUALOPERATINGREPORTM 6.9.1.4 Annual reports covering the activities of the unit during the previous calendar year shall be submitted prior to March 31 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality. 6.9.1.5 Reports required on an annual basis shall include:
- a. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their a "accordingtoworkandjobfunctions,.gociatedmanremexposure e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (described 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. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions,
- b. The complete results of steam generator tube inservice inspections (Specification 4.4.5.5.b).
MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics, shutdown experience and challenges to the Pressurizer Power Operated Relief Valve (PORV) and the Pressurizer Code Safety Valves shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Consnission, Washington. 0.C. 20555, with a copy to the Regional Office, to arrive no later than the 15th of each month following the calendar month covered by the report. E A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station, b This tabulation supplements the requirements of 120.407 of 10 CFR Part 20.
. DAVIS-BESSE, UNIT 1 6-15 Amendment No. 7, N . M . E ,
i lis 87 1 1
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i s e O l 1 I l DAVIS-8 ESSE, UNIT 1 6-16 Amendment No. 3, JJ, 93 l r
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