ML20132C982

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Forwards Final Draft Facility Tech Specs for Review.Review Results Should Be Provided to Tech Spec Review Group by 850513
ML20132C982
Person / Time
Site: River Bend Entergy icon.png
Issue date: 04/19/1985
From: Crutchfield, Crutchfield D
Office of Nuclear Reactor Regulation
To: Harold Denton
NRC
Shared Package
ML20132C450 List:
References
FOIA-85-511 NUDOCS 8505020572
Download: ML20132C982 (40)
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April 19, 1985 MEMORANDUM FOR: Those on Attached List FROM:

Dennis M. Crutchfield, Assistant Director for Safety Assessment Division of Licensing Thomas M. Novak, Assistant Director for Licensing Division of Licensing

SUBJECT:

FINAL DRAFT OF THE RIVER BEND UNIT 1 TECHNICAL SPECIFICATIONS The attached final draft technical specifications for River Bend Unit 1 (enclosure 1) are being forwarded to you at this time for review. We request that you review those sections which pertain to your particular area of responsibility and that the results of this review, identifyino th

' "Y l} D e sections reviewed, be forwarded to the Technical Specification Review em (TSPG) by May@l985. We ere distributing these technical speci-fications at the nkk ' branch level, however, we request that the responses be consolidated, reviewed and returned at the Assistant Director level.

By issuing these technical specifications in the final draft form at this time without benefit of a fomal proof and review period between the second draft and the final draft, we are making a significant deviation from our nomal technical specification preparation process. This deviation is being made in the interest of expediting the review process 50 as not to unneces-sarily delay the planned plant startup date of some time in June 1985. It is important to note, however, that even though we are skipping one of the steps in the preparation process we are not skipping any of the steps in our j

independent review and certification process to assure the safety adequacy of the technical specifications. These steps, such as, the NRC Regional review, the internal NRC technical branch reviews, the independent NRC consultant review, and the applicants certification'of the correctness of the technical specifications will be performed as shown on the enclosed marked up schedule for River Bend (enclosure 2).

This is a very ambitious schedule we will be working to and will require the complete cooperation of all th9 parties involved. The schedule has been reviewed by both the NRC and applicant's management and has been established as the goal both organizations will be striving to achieve, q

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. April 19, 1985 In making judgements about the correctness or adequacy of these technical specifications for River Bend you should be guided by the principles of NRR Office Letter No. 38. Deviations from the (CE) STS should not be proposed or accepted by the staff or applicant unless they are:

(1) necessary because of unique design features or unique organization characteristics, or (2) represent e significant improvement over the STS which should be included in the next revision to the STS and do not y

represent a change in generic recuirements whTch must be reviewed prior to implementation by CRGR.

Deviations from the STS which have merit but are generic and require CRGR review should not be proposed at this tirne for River Bend. Instead they should be processed thru CRGR as a revision to the STS which can later be applied to River Bend at the licensee's reouest or as a backfit by the staff.

Those generic changes involving an -ireediate safety concern should, however, not be delayed for CRGR review. Any such cases should be highlighted for expedited action by DL and other appropriate NRC Divisions.

Mr. Dean Houston, of TSRG will be available during the final review period to answer any questions which arise. He is located in Room 521, of the Phillips Building and his telephone nurnber is 49-28933.

Even if you have no consnents and are in agreement with the technical specifications content in your area of review, it is requested that a written response to that effect identifying those sections of the technical specifications reviewed be provided by the above specified date.

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Dennis M.

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d. As stant Director for Safety Assessment Division of Licensing Thomas M. Novak, Assistant Director for Licensing Division of Licensing

Enclosures:

1.

River Bend Nuclear Power Plant, Unit 1 Technical Specifications 2.

River Bend marked up schedule t

cc: w/o enclosure see next page.

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. April 19, 1985 CC: h/o enclosure H. Denton H. Thompson T. Speis J. Knight R. Bernero W. Russell G. Lainas F. Schroeder F. Rowsome W. Johnston

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R. Houston L. Rubenstein D. Muller R. Bosnak D. Beckham D

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Distribution for River Bend Unit 1 Date: April 19,1985 ATTACHED LIST Al Schwencer, Chief Olan D. Parr, Chief Licensing Branch No. 2, DL Auxiliary Systems Branch, DSI Gary Holahan, Chief William P. Gammill, Chief Operating Reactors Assessment Meteorology and Effluent Branch, DL Treatment Branch, DSI S. D. Liaw, Chief Lewis G. Hulman, Chief #

Materials Engineering Branch, DE Accident Evaluation Branch, DSI Victor Benaroya, Chief Frank Congel, Chief Chemical Engineering Branch, DE Radiological Assessment Branch, DSI Vincent Noonan, Chief William Regan, Acting Chief Equipment Qualification Branch, DE Human Factors Engineering Branch, DHFS Robert E. Jackson, Chief Dennis Ziemann, Chief Geosciences Branch, DE Procedures & Systems Review Branch, DHFS George Lear, Chief Robert D. Martin Structural & Geotechnical Reofonal Administrator Engineering Branch, DE Region IV Ronald L. Ballard, Chief John Jaudon Environmental & Hydrologic Senior Resident Inspector Engineering Branch, DE Region IV William H. Regan, Chief Harold R. Booher, Chief Site Analysis Branch, DE License Oualifications Branch, DHFS Frank C. Cherny, Acting Chief Mechanical Engineeri' g Branch, DE n

Brian W. Sheron, Chief Peactor Systems Branch, DSI Faust Rosa, Chief G. Ted Ankrum, Chief Instrumentation & Control Quality Assurance Branch, IAE Systems Branch, DSI Walter R. Butler, Chief Steve Stern, Project Manager Containment Systems Branch, DSI Licensing Branch No. 2. DL M. I. Srinivasan, Chief Applicant: (3)

Power Systems Branch, DSI Carl Berlinger, Chief Core Perfortnance Branch, DSI

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6. 5.1. 5 The quorum of the FRC necessary for the performance of the FRC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including no more than two alternates.

RESPONSIBILITIES

6. 5.1. 6 The FRC shall be responsible for:

Review of all plant general administrativ$ a. thereto; procedures and changes b. Review of all proposed tests and experiments that affect nuclear safety; Review of all proposed enanges to Appe ix A c ica) pecifi ' ns; c. gk d. Review of all proposed O': ; : 9 e r s%Andst t /A 4CY G/Vf r :- mod ations to structures, compo-nents, systems or equipment tnat affect nuclear safety; Investigation of all violations of the Technical Specifications, e. including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the Nuclear Review Board; f. Review of all REPORTABLE EVENT 5; Review of unit operations to detect potential hazards to nuclear safety, g. items that may be included in this review are NRC inspectio9

reports, QA audits / surveillance reports of operating and maintenance activities, NRB audit results, and American Nuclear Insurer (ANI) inspection results; Performance of special reviews, investigations, or analyses and reports h.

thereon as requested by the Plant Manager or the Nuclear Review Board; and i. 6U Review of initial start-up testing phase start up procedures and revisions, y p s fue, of +ht. Emargesy Pwympte ms*st@ pmmu eats pu* i2 nucn As a..a e--- Je

6. 5.1. 7 The FRC shall:

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e. & m,, a-Recommend in writing to the Plant Manager approval or disapproval of a.

items considered under Specification 6.5.1.6.a. through d. prior to their implementation. b. Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6.a. through e. constitutes an unreviewed safety questien. Provide written notification within 24 hours to the Vice President - c. RBNG and the Nuclear Review Board of disagreement between the FRC and the Plant Manager; however, the Plant Manager shall have respon-sibility for resolution of such disagreements pursuant to Specifica-tion 6.1.1. RIVER BEND - UNIT 1 6-8 W!6M

FINAL DRAFT ADMINISTRATIVE CONTROLS RECORDS The FRC shall maintain written minutes of each FAC meeting that, at a 6.5.1.8 minimum, document the results of all FRC activities performed under the respon-sibility provisions of these Technical Specifications. Copies shall be provided 1 l to the Plant Manager and the NR8.

6. 5. 2 TECHNICAL REVIEV AND CONTROL 6.5.2.1 Each procedure and program required by Specification 6.8'and other pro-cedures that af fact nuclear safety, and changes thereto, is prepared by a quali-fied individual / organization. Each such procedure, and changes thereto, shall i

be reviewed by an individual / group other than the individual / group that prepared .he procedure, or changes thereto, but who may be from the same organization as the individual / group that prepared the procedure. Each such procedure and pro-gram, or changes thereto, shall be approved, prior to implementation, by the Q Plant Manager or one of the Assistant Plant Managers 'or the Supervisor - Recto-Q' 6g logical Progrars with the exce k:;=;y %h =the ":u;.ption of the Emergency 7aplementing/rocedures. 4

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- C n.itt;; = the gpproved by thejPlant Manager and Vice President - R8NG. Wnoek s w tbc z ma n,y, _ p g g,,,q,,4;m, 6.5.2.2 Individuals responsible for reviews performed in accordance with Sec-tion 6.5.2.1 shall be seabers of River Send Nuclear Group supervisory staff, and the reviews performed in accordance with administrative procedures. Each such review shall include a determination of whether or not additional, cross-disciplinary review is necessary and a verification that the proposed actions do not constitute an unreviewed safety question. If deemed necessary, such review shall be performed by the appropriate designated review personnel. 6.5.2.3 The station security program and faplementing procedures shall be reviewed at least once per 12 months, and recommended changes approved in at-cordance with Specification 6.5.2.1. OL 6.5.2.4 The station emergency plan and implementing procedures ;M h r; y a_- 3_... - t ance with Specification 6.5.2.1.% and recommended changesyapproved in accord-shalt ba. 6.5.2.5 The station fire protection plan and taplementing procedures shall be reviewed at least once per 12 months, and recommended changes approved in accordance with Specification 6.5.2.1. 6.5.2.6 Reports documenting each of the* activities performed under Specifica-tions 6.5.2.1 through 6.5.2.5 shall be maintained. 6.5.3 NUCLEAR REVIEW BOARD (NR$) FUNCTION 6.5.3.1 The NRB shall function to provide independent review and audit of designated activities in the areas of: RIVER BEND - UNIT 1 6-9 M 2 8 M5 t

ADMINISTRATIVE CONTROL ~~

== &).V , MONTHLY OPERATING REPORTS / /4 I '~ jf .d h 6.9.1.6 Routine reports of operating 4tatistics and shutdown experience cio r;; h-^9tatica e' ei! @ ei!ean P ic the nia stes-Sys+== ** fat;/ e!ie n. r u=1oael shall be submitted on a monthly basis to the Director, Office of Resource $g' ManageInent, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC no later than the 15th of each month following the calendar month covered by the report. ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.7 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality. The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiologica environmental surveillance activit.ies for the report period, including a comp [ar-ison (as appropriate), with preoperational studies, operational controls and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 3.12.2. C The Annual Radiological Environmental Operating Reports shall include the results cf all radiological environmental samples and of all environmental radiation measurements taken during the report period pursuant to the locations specified in the tables and figures in the OFFSITE DOSE CALCULATION MANUAL, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Brt.nch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the rease-s for the missing results. The missing data shall be suumitted as soon as possiele in a supplementary report. The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps" covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor plant; the results of ifcensee participaticn in the Interlaboratory Comparison Program, required by Specification 3.12.3; discussion of all deviations from the Sam discussion of all analyses in vhich the (pling Schedule of Table 4.12.1-1; and LD required by Table 4.12.1-1 was not actit Wale. "One map shall cover stations near the SITE BOUNDAP.Y; a second shall include the more distant stations, s RIVER BEND - UNIT 1 6-17 API 2 61985

ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories. Records of radiation exposure for all individuals entering radiation c. control areas. d. Records of gaseous and liquid radioactive material released to the environs. Rec &ds of transient or operational cycles for those unit components e. identified in Table 5.7.1-1. f. Records of reactor tests and experiments. g. Records of training and qualification for current members of the unit staff. g h. Records of inservice inspections performed pursuant to these Technical Specifications. i. Records of quality assurance activities required by the Operational Quality Assurance Manual not listed in Section 6.10.1. j. Records of reviews performed for char.ges made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59. bU 7 sp k. Records of meetings of U.e C,. rn;, "h- 'n; M it:: (CPC y the g pa. FRC and the NRB. 1. Records of the service lives of all snubbers including the date at which the service life commences and associated installation and maintenance records. 6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared con-sistent with the reovirements of 30 CFR Part 20 and shall be approved, main-tained, and adhered to for all operations involving personnel radiation exposure. 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 arem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto RIVER BEND - UNIT 1 6-21

1 1 I l FIMt..?y< -a.'a r, i j TECHNICAL SPECIFICATIONS RIVER BEND - UNIT 1 I APR 2 61985

FINAL DRMT 9 SECTION 6.0 ADMINISTRATIVE CONTROLS 6 O l l l I l Apg 2 61985 ~ -- ' '* 999 9 e *,,. -e r- -wwy-.m y, 9 ,.-----.-,..yy,,---,."*"r""--"r'"*-" ""P"-'"-**""+

6.0 ADMINISTRATIVE CONTROLS I 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence. 6.1. 2 The Shift Supervisor (or during his absence from the control room, a X Amanagementdirectiv)etothiseffect,signedbytheSeniorVicePresident-desig

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River Bend Nuclear Group 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 E.2.2 The unit organization shall be as shown on Figure 6.2.2-1 ant Each on; duty shift shall be composed of at least the minimum shif t )( a. 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. In addition, while the unit is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Operator shall be in the control room; A Radiation Protection Technician" shall be on site when fuel is in c. the reactor; All CORE ALTERATIONS shall be observed and directly supervised by d. either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; A site fire brigade of at least (ive members shall be maintained on e. site at all times". The fire brigade shall not include the Shift Supervisor, the Shift Technical Advisor, the Control Operating Foreman, nor the two other 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; and "The Raciation Protection Technician and fire brigade composition ray be less than the minimum requirements for a period of time net to exceed 2 hours, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions. RIVER BEND - UNIT 1 6-1 MPS26Eg3

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ADMINISTRATIVE CONTROLS am WJa a u UNIT STAFF (Continued) f. Administrative procedures shall be developed and implemented to limit ralklien gefedian i the workino hours of unit staff who perform safety-related functions ge,nicians, Jr(e.g., licensed Senior Operators, licensed operators,tdth ph:,-i='*~ s g, auxiliary operators, and key maintenance personnel). Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a nominal 40-hour week while the unit is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refue-ling, major maintenance, or major unit modifications, on a temporary basis the following guidelines shall be followed: 1. An individual should not be permitted to work more than 16 hours straight, excluding shift turnover time. 2. An individual should not be permitted to work more than 16 hours in any 24-hour period, nor more than 24 hours in any 48-hour period, nor more than 72 hours in any seven day period, all excluding shift turnover time. 3. A break of at least eight hours should be allowed between work periods, including shift turnover time. 4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift. Any deviation from the above guidelines shall be authorized by the Plant Manager or either one of the Assistant Plant Managers or the Supervisor-Radiological Programs, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized. RIVER BEND - UNIT 1 6-2 UE I O IES

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FINAL DRAFT TABLE 6.2.2-1 MINIMUM SHIFT CREW COMPOSITION SINGLE UNIT FACILITY POSITION NUMBER OF INDIVIOUALS REQUIRED TO FILL POSITION CONDITION 1, 2, or 3 CONDITION 4 or 5 SS 1 1 SRO 1 None R0 2 1 A0 2 1 STA" 1 None TABLE NOTATION SS - Shift Supervisor with a Senior Operator license on Unit 1. SRO - Individual with a Senior Operator license on Unit 1. RO - Individual with an Operator license on Unit 1. AO - Auxiliary operator STA - Shift Technical Advisor

  • The Shift Technical Advisor (STA) position may be filled by an on-shift Shift Supervisor (SS) or Senior Reactor Operator (SRO) provided the individual meets the STA qualifications of Specification 6.2.4 and five (5) licensed operators are on shift.

The shift crew composition may be one less than the minimum requirements of Table 6.2.2-1 for a period of time not to exceed 2 hours in order to accommo-date unexpected absence of on-duty shift crew members provided immediate action' is taken to restore the shift crew composition to within the minimum require-ments 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. During any absence of the Shift Supervisor from the control room while the unit is in OPERATIONAL CONDITION 1, 2 or 3, an individual with a valid Senior Operator license shall be designated to assume the. control room command function. During any absence of the Shift Supervisor from the control roem while the unit is in OPERATIONAL CONDITION 4 or 5, an individual with a valid Senior Operator license or Operator license shall be designated to assume the control room command function. 8 RIVER BEND - UNIT 1 6-5 ...... -.... n..., ..- - -- ~ ~'~ ~ ~ ~ ~

FINAL. DTGR ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) FUNCTION 6.2.3.1 The ISEG shall function to examine i, nit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating experience information, including units of simi-lar design, which may indicate areas for improving unit safety. The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving unit safety to the Vice President - Safety and Environment. I COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time ef which] or related science and at least 2 years professional level experience in h engineers located onsite. j hha# h t i field,atleast1 yea]experiencepnthenuclearfield. RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification

  • that these activities are per-formed correctly and that human errors are reduced as much as practical.

RECORDS 6.2.3.4 Records of activities performed by the ISEG shall be prepared, main-tained, and fomarded each calendar month to the Vice President - Safety and Environment. 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineer-ing discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentagion and controls in the control room. For the dual role position shown in Table 6.2.2-1, the Shift Technical Advisor CK shall have a bachelor's degree or shall have completed all technical courses required for the degree in a scientific er engineering discipline and shall have received all of the trainihg for the normal STA position described above. "Not responsible for sign-off function. RIVER BEND - UNIT 1 6-6 M26E ..,..s.....-.

FINAL DRAFT ADMINISTRATIVE CONTROLS

6. 3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI /ANS 3.1-1978 for comparable positions, except for the Supervisor-Radiological Programs who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees. 6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager-Administration,shall meet or )( exceed the requirements and recommendations of Section 5.5 of ANSI /ANS 3.1-1978 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licenhees, and shall include familiarization with relevant industry operational experience. 6.5 REVIEW AND AUDIT 6.5.1 FACILITY REVIEW COMMITTEE (FRC) FUNCTION 6.5.1.1 The FRC shall function to advise the Plant Manager on all matters related to nuclear safety. COMPOSITION

6. 5.1. 2 The FRC shall be composed of the:

Chairman: Assistant Plant Manager-Technical Services Member: Assistant Plant Manager-Operations, Radwaste and Chemistry Member: Assistant Plant Manager-Maintenance and Material Member: General Operations Supervisor Member: Supervisor-Radiological Program Member: Reactor Engineering Supervisor ALTERNATES

6. 5.1. 3 All alternate members shall be appointed in writing by the FRC Chairman to serve on a temporary basis; however, no more than two alternates shall partici-pate as voting members in FRC activities at any one time.

MEETING FREQUENCY

6. 5.1. 4 The FRC shall meet at least once per calendar month and as convened by the FRC Chairman or his designated alternate.

RIVER BEND - UNIT 1 6-7 APF 2 6 EES ..n -...,..,. _. _ --,.-.~.

ADMINISTRATIVE CONTROLS QUORUM 6.5.1.5 The quorum of the FRC necessary for the performance of the FRC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and[,oud members including f no more than two alternates. t g,> co.// he reabee/ h thru me btes sT o'eUred. RESPONSIBILITIES 6.5.1.6 The FRC shall be responsible for: Review of all plant general administrative procedures and changes a. thereto; b. Review of all proposed tests and experiments that affect nuclear safety; Review of all proposed changes to Appendix A Technical Specifications; .- c. d. Review of all proposed changes or modifications to structures, compo-nents, systems or equipment that affect nuclear safety; v.h fru de,,4 e. Investigation of all violations of the Technical Specific'tions, a tsNQ ,..J N, includina the preparation and forwarding of rep ts covering evaluation and recommendations to prevent recurrence, to the Nuclear Review Board; - f. Review of all REPORTABLE EVENTS; ,g. Review of unit operations to detect potential hazards to nuclear safety, items that may be included in this review are NRC inspection reports, QA audits / surveillance reports of operating and maintenance activities, NR8 audit results, and American Nuclear Insurer (ANI) inspection results; h. Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant Manager or the Nuclear Review Board; and i. Review of initial start up testing phase start-up procedures and revisions. 6.5.1.7 The FRC shall: Recommend in writing to the Plant Manager approval or disapproval of a. items considered under Specification 6.5.1.6.a. through d. prior to their implementation. b. Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6.a. through e. constitutes an unreviewed safety question. ~ Provide written notification within 24 hours to the Vice President - c. R8NG and the Nuclear Review Board of disagreement between the FRC and the Plant Manager; however, the Plant Manager shall have respon-sibility for resolution of such disagreements pursuant to Specifica-tion 6.1.1. RIVER BEND - UNIT 1 6-8 APR 2 61985 ....._.s........

FINAL DRAFf ADMINISTRATIVE CONTROLS RECORDS 6.5.1.8 The FRC shall maintain written minutes of each FRC meeting that, at a minimum, document the results of all FRC activities performed under the respon-sibility provisions of these Technical Specifications. Copies shall be provided to the Plant Manager and the NRB. 6.5.2 TECHNICAL REVIEW AND CONTROL 6.5.2.1 Each procedure and program required by Specification 6.8 and other pro-cedures that affect nuclear safety, and changes thereto, is prepared by a quali-fied individual / organization. Each such procedure, and changes thereto, shall be reviewed by an individual / group other than the individual / group that prepared the procedure, or changes thereto, but who may be from the same organization as the individual / group that prepared the procedure. Each such procedure and pro-gram, or changes thereto, shall be approved, prior to implementation, by the Plant Manager or one of the Assistant Plant Managers or the Supervisor - Radio-logical Programs with the exception'of the Emergency Implementing Procedures. Emergency Implementing Procedures are reviewed by the Emergency P1arnning Committee and then approved by the Plant Manager and Vice President - RBNG. 6.5.2.2 Individuals responsible for reviews performed in accordance with Sec-tion 6.5.2.1 shall be members of River Bend Nuclear Group supervisory staff, and the reviews performed in accordance with administrative procedures. Each such review shall include a determination of whether or not additional, cross-disciplinary review is necessary and a verification that the proposed actions do net constitute an unreviewed safety question. If deemed necessary, such review shall be performed by the appropriate designated review personnel. 6.5.2.3 The station security program and implementing procedures shall be reviewed at least once per 12 months', and recommended changes approved in ac-cordance with Specification 6.5.2.1. 6.5.2.4 The station emergency plan and implementing procedures shall be re-viewed at least once per 12 months, and recommended changes approved in accord-ance with Specification 6.5.2.1. 6.5.2.5 The station fire protection plan and implementing procedures shall be reviewed at least once per 12 months, and recommended changes approved in accordance with Specification 6.5.2.1. 6.5.2.6 Reports documenting each of the activities performed under Specifica-tions 6.5.2.1 through 6.5.2.5 shall be maintained. 4 6.5.3 NUCLEAR REVIEW BOARD (NRB) FUNCTION 6.5.3.1 The NRB shall function to provide independent review and audit of designated activities in the areas of: RIVER BEND - UNIT 1 6-9 M 2 6 H15 ,...,... ~,..... _

I FINAL D8 RAFT ADMINISTRATIVE CONTROLS FUNCTION (Continued) a. Nuclear power plant operations, i b. Nuclear engineering, c. hemistry and radiochemistry, d. Metallurgy, e. Instrumentation and control, 1 f. Radiological safety, g. Mechanical and electrical engineering. h. Quality assurance practices, 1. Licensing and regulatory affairs, j. Training. i The NRB shall report to and advise the Senior Vice President - RBNG on those i areas of responsibility in Specifications 6.5.3.7 and 6.5.3.8. COMPOSITION 6.5.3.2 The NRB shall be composed of the: j Chairman: Vice President - Safety and Environment Member and Vice Vice President - RBNG Chairman Member: Manager - Administration Member: Executive Vice President-External Affairs and Production Member: Manager-Design Engineering, Technical Services Department Member: Manager-Engineering, Nuclear Fuels, and Licensing Member: Plant Manager Member: Assistant Plant Manager-Operations, Radwaste and Chemistry Member: Manager-Quality Assurance Member: Director-Nuclear Licensing I Member: Director-Nuclear Plant Engineering l Member: Director-Nuclear Fuels Design and Safety Analysis ALTERNATES 6.5.3.3 All alternate members shall be appointed in writing by the NRB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in NRB activities at any one time. CONSULTANTS 6.5.3.4 Consultants shall be utilized as determined by the NRB Chairman to provide expert advice to the NRB. RIVER BEND - UNIT 1 6-10 y 161!25 .......,,........ ~,..... - =...... .... - ~

FINAL DRAFT ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.3.5 The NRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter. QUORUM 6.5.3.6 The quorum of the NRB necessary for the performance of the NRB review and audit functions of these Technical Specifications shall consist of the Chairman or the Vice Chairman and at least six NRB members including no more than two alternates. No more than a minority of the quorum shall have line responsibility for operation of the unit. REVIEW be respensible fer the ruitw of : 6.5.3.7 The NR8 shall,rovies-The safety evaluations for (1) changes to procedures, equipment, or a. systems; and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question; b. Proposed changes to precedures, equipment, or systems which involve an'unreviewed safety question as defined in 10 CFR 50.59; Proposed tests or experiments which involve an unreviewed safety c. question as defined in 10 CFR 50.59; Proposed changes to Technical Specifications or this Operating License; d. Violations of codes, regulations, orders, Technical Specifications, e. license requirements, or of internal procedures or instructions having nuclear safety significance; f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; g. All REPORTABLE EVENTS: h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and t i. Reports and meeting minutes of the FRC. AUDITS 6.5.3.8 Audits of unit activities shall be performed under the cognizance of the NRB. These audits shall encompass: RIVER BEND - UNIT 1 6-11 W26E

FINAL DRAFT ADMINISTRATIVE CONTROLS AUDITS (Continued) a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 mc.nths; b. The performance, training and qualifications of the entire unit staff at least once per 12 months; The results of actions taken to correct deficiencies occurring in c. 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 Operational Quality Assurance Program to meet the criteria of Appendix 8, 10 CFR Part l 50, at least once per 24 months; The fire protection programmatic controls including the implementing e. procedures at least once per 24 months by qualified licensee QA personnel; l f. The fire protection equipment and program implementation at least once per 12 months utilizing either qualified offsite licensee personnel or an outside independent fire protection consultant. An outside independent fire protection consultant shall be utilized at least every third year; and g. Any other area of unit operation considered appropriate by the NRB, Plant Manager or tne Senior Vice President - R8NG. h. The Emergency Plan and implementing procedures at least once per 12 months. i. The Security Plan and implementing procedures at least once per 12 months. j. The radiological environmental monitoring program and the results thereof at least once per 12 months. k. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at i least once per 24 months. 1. The PROCESS CONTROL PROGRAM and implementing pr)cedures for solidifi-cation of radioactive wastes at least once per 24 e.onths, The performance of activities by the Quality Assurance Program to m. meet the criteria of Regulatory Guide 4.15 at least once per 12 months. RECORDS 6.5.3.9 Records of NRB activities shall be prepared, approved, and distributed as indicated below: RIVER BEND - UNIT 1 6-12 m t 6 MS

FINAL DRK7 ADMINISTRATIVE CONTROLS RECORDS (Continued) Minutes of each NRB meeting shall be prepared, approved, and forwarded a. to the Senior Vice President - RBNG within 14 days following each meeting. b. Reports of reviews encompassed by Specification 6.5.3.7 shall be prepared, approved, and forwarded to the Senior Vice President - RBNG within 14 days following completion of the review. Audit reports encompassed by Specification 6.5.3.8 shall be forwarded c. to the Senior Vice President - RBNG and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization,

6. 6 REPORTABLE EVENT Acr/ M g

6.6.1 The following actions shall be taken for REPORTABLE EVENTS: The Commission shall be notified and a report submitted pursuant to a. the requirements of 10 CFR 50.73 and b. Each REPORTABLE EVENT shall be reviewed by the FRC and the results of this review shall be submitted to the NR8 and the Plant Manager. - 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: The NRC Operations Center shall be notified by telephone as soon as a. possible and in all cases within I hour. The Senior Vice President - RBNG and the NRB chairman (or personnel acting for their function) shall be notified within 24 hours, b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the FRC. 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. The Safety Limit Violation Repor't shall be submitted to the Commission, c. the NRB, and the Senior Vice President - RBNG within 14 days of the ' violation. d. Critical operation of the unit shall not be resumed until authorized l by the Commission. 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below: RIVER BEND - UNIT 1 6-13 gR 16 N

FINAL DilAFT ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) The applicable procedures recommended in Appendix A of Regulatory a. Guide 1.33, Revision 2, February 1978. b. The applicable procedures required to implement the requirements of NUREG-0737 and stepplements thereto. - c. Refueling operations. d. Surveillance and test activities of safety-related equipment. e. Security Plan implementation. - f. Emergency Plan implementation. , g. Fire Protection Program implementation. - h. Process Control Program implementation. 1. Offsite Dose Calculation Manual implementation. 1 -j. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15. i 6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed and approved in accordance with Specification 6.5.2.1. 6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made pro-viced: The intent of the original procedure is not altered; a. The change is approved by two members of the plant management staff, b. at least one of whom holds a Senicr Operator license on the unit affected; and The change is documented, reviewed by the FRC, and approved in accord-c. ance with Specification 6.5.2.1 within 14 days of implementation. 6.8.4 The following programs shall be established, implemented, and maintained: Primary Coolant Sources Outside Containment .a. A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the HPCS, LPCS, RHR, RCIC, process sampling and standby gas treatment systems. The program shall include the following: 1. Preventive maintenance and periodic visual inspection requirements, and RIVER BEND - UNIT 1 6-14 W26% }

ADMINISTRATIVE CONTROLS =a PROCEDURES AND PROGRAMS (Continued) 2. Integrated leak test requirements for each system at refueling cycle intervals or less. b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following: 1. Training of personnel, 2. Procedures for monitoring, and 3. Provisions for maintenance of sampling and analysis equipment, c. Post-accident Sampling A nrogram which will ensure the capability to obtain and* analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident I conditions. The program shall include the following: 1. Training of personnel, 2. Procedures for sampling and analysis, and 3. Provisions for maintenance of sampling and analysis equipment. d. Biofouling Prevention and Detection A program, approved by the NRC Staff prior to introduction of riv'er water to the systems, which will ensure the procedures to prevent biofouling of safety-related equipment, assure detection of Corbicula in the intake embayment and the Mississippi River at the River Bend Station site, and monitor and survey safety-related equipment to de-tect biofouling. Changes to this program will be submitted to and i approved by the NRC prior to implementation. I 6.9 REPORTING REQUIREMENTS 4 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 Regional Administrator of the Regional Office of the NRC unless otherwise noted. STARTUP REPORT

6. 9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to RIVER BEND - UNIT 1 6-15 APS28885

ADMINISTRATIVE CONTROLS STARTUP REPORT (Continued) the license involving a planned increas wer level, (3) installation of fuel that has a different design or h been manufactured by a different fuel supplier, and (4) modifications th may have significantly altered the nuclear,, thermal, or hydraulic p formance of the unit. 6.9.1.2 The startup report s 11 address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured 4 values of the operating conditions or characteristics obtained during the test I program and a comparison of these values with design predictions and specifica-l 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 included in this report. 6.9.1.3 Startup reports shall be submitted within (1) 90 days following comple-tion of the startup test program, (2) 90 days following resumption or commente-ment 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 commencement of commercial op? ration) supplementary reports shall be submitted at least every 3 months until all three events have been completed. ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 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 tabulation on an annual basis of the number of station, utility, a. and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man-rem exposure according to work and job functions * (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance waste processing, and refueling). The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge geasurements. 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 should be assigned to specific major work functions; b. Documentation of all challenges to safety / relief valves. "This tabulation supplements the requirements of $20.407 of 10 CFR Part 20. RIVER BEND - UNIT 1 6-16 p 16 5

4 ubb& ne d a a E ADMINISTRATIVE CONTROL MONTHLY OPERATING REPORTS 6.9.1.6 Routine reports of operating statistics and shutdown experience (in-cluding documentation of all challenges to the main steam system safety / relief valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC no later than the 15th of each month foilowing the calendar month covered by the report. ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.7 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality. The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological ~ environmental surveillance activities for the report period, includ'ing a compar-ison (as appropriate), with preoperational studies, operational controls and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 3.12.2. The Annual Radiological Environmental Operating Reports shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the report period pursuant to the locations specified in the tables and figures in the OFFSITE DOSE CALCULATION MANUAL, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps" covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor plant; the results of licensee participation in the Interlaboratory Comparison Program,* required by Specification 3.12.3; discussion of all deviations from the Sampling Schedule of Table 4.12.1-1; and discussion of all analyses in which the LLO required by Table 4.12.1-1 was not achievable. "One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations. RIVER BEND - UNIT 1 6-17 APR 2 619E

F M DRAFT ADMINISTRATIVE CONTROLS SEMIANNUAL EFFLUENT RELEASE REPORT 6.9.1.8 Routine Semiannual Radioactive Effluent Release Raports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The period of the first report shall begin with *.he date of initial criticality. The Semiannual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1. June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. The Semiannual Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed l wind direc-tion and atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind directon, atmospheric stability.* This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figures 5.1.3-la and 5.1.3-lb) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The assessment of radiation doses shall be performed in accordance with the methodology and parameters of the OFFSITE DOSE CALCULATION MANUAL (ODCM). The Semiannual Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1, October 1977. The Semiannual Radioactive Effluent Release Reports shall include the following information for each type of solid waste (as defined in 10 CFR Part 61) shipped offsite during the report period: "In lieu of submission with the first half year Semiannual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request. RIVER BEND - UNIT 1 6-18 APR 2 61!BS

ADMINISTRATIVE CONTROLS SEMIANNUAL EFFLUENT RELEASE REPORT (Continued) a. Container volume, b. Total curie quantity (specify whether determined by measurement or

estimate, c.

Principal radionuclides (specify whether determined by measurement or estimate), d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms), Type of container (e.g., LSA, Type A, Type B, Large Quantity), and e. SOLIDIFICATION agent or absorbent (e.g., cement; urea formaldehyde). f. The Semiannual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the re, porting period. The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the ODCM, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specifi-cation 3.12.2 Arm 2sse3 RIVER BEND - UNIT 1 6-19

FINAL DRAFT ADMINISTRATIVE CONTROLS SPECIAL REPORTS i 5.9.2 Special reports shall be submitted in the following manner: Special reports shall be submitted to the Regional Administrator of a. the Regional Office of the NRC within the time period specified for each report. b. Special reports in regard to Corbicula will be submitted in accord-dance with the settlement agreement dated October 10, 1984. 6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated. 6.10.2 The following records shall be retained for at least 5 year,s: Records and logs of unit operation covering time interval at each a. 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. Records of changes made to the procedures required by Specification e. 6.8.1. 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 sealtd source material of record. = 1. Records of analyses required by the radiological environmental monitoring program. j. Records of emergency drills and exercises. 6.10.3 The following records shall be retained for the duration of the unit Operating License: Records and drawing changes reflecting unit design modifications made a. to systems and equipment described in the Final Safety Analysis Report. RIVER BEND - UNIT 1 6-20 M 2 61985

al ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories. Records of radiation exposure for all individuals entering radiation c. control areas. d. Records of gaseous and liquid radioactive material released to the environs. Records of transient or operational cycles for those unit components e. identified in Table 5.7.1-1. f. Records of reactor tests and experiments. g. Records of training and qualification for current members of the unit staff. h. Records of inservice inspections performed pursuant to th'ese Technical Specifications. i. Records of quality assurance activities required by the Operational Quality Assurance Manual not listed in Section 6.10.1. j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59. k. Records of meetings of the Emergency Planning Committee (EPC), the FRC and the NRB. 1. Records of the service lives of all snubbers including the date at which the service life commences and associated installation and maintenance records. 6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, main-tained, and adhered to for all operations involving personnel radiation exposure. 6.12 HIO'l RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 arem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto 4PR 2 6 ses RIVER BEND - UNIT 1 6-21 ._ i

F NI M8 M h4 T d ab. ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) shall be controlled by requiring issuance of a Radiation Work Permit (RWP)* Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following: 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 received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them. A radiation protection qualified individual (i.e., qualified in radia-c. tion protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveil-lance at the frequency specified by the Health Physicist in the RWP. 6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Control Operating Foreman on duty and/or the radiation protection supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in I hour a dose in excess of 1000 mrem"* that are located within large areas, sucfi as the containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted, and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, continuous surveillance direct or remote (such as use of closed circuit TV cameras), may be made by personnel qualified in radiation protection pro-cedures to provide positive exposure control over the activities within the area. "Raciation protection personnel or personnel escorted by radiation protection personnel shall be exempt from the RWP issuance requirement during the perfor-mance of their assigned radiation protection duties, provided they are other-wise following plant radiation protection procedures for entry into high radiation areas.

    • Measurement made at < 18 inches from source of radioactivity.

RIVER BEND - UNIT 1 6-22 g 16125

FINAL DRRn ADMINISTRATIVE CONTROL 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation. 6.13.2 Licensee initiated changes to the PCP: 1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain: Sufficiently detailed information to totally support the rationale a. for the change without benefit of additional or supplemental information; b. A determination that the change did not reduce the overall confor-mance of the solidified waste product to existing criteria for solid wastes; and Documentation of the fact that the change has been r.eviewed and c. found acceptable pursuant to Specification 6.5.2. 2. Shall become effective upon review and acceptance pursuant to Speci-fication 6.5.2. 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation. 6.14.2 Licensee initiated changes to the ODCM: 1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain: Sufficiently detailed information to totally support the rationale a. for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and data box, together with appro-priate ' analyses or evaluati,ons justifying the change (s); b. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c. Documentation of the fact that the change has been reviewed and found acceptable pursuant to Specification 6.5.2. 2. Shall become effective upon review and acceptance pursuant tc Speci-fication 6.2.2. i RIVER BEND - UNIT 1 6-23

O FIEl DMFT ADMINISTRATIVE CONTROL 6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid): 1. Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed pursuant to Specification 6.5.2. The discussion of each change shall contain: A summary of the evaluation that led to the determination that a. the change could be made in accordance with 10 CFR Part 50.59. b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; A detailed description of the equipment, components,and processes c. involved and the interfaces with other plant systems; d. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; An evaluation of the change, which shows the expected maximum e. exposures to individual in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto; f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; g. An estimate of the exposure to plant operating personnel as a result of the change; and h. Documentation of the fact that the change was reviewed and found acceptable pursuant to Specification 6.5.2. 2. Shall become effective upon review and acceptance pursuant to Speci-fication 6.5.2. RIVER BEND - UNIT 1 6-24 MR 2 6 35 '14

3. y eem.e-.

_e ~e mo 7 w - +"*~,'p**

l 7 E[', ea.m), UNITED STATES 'h NUCLEAR REGULATORY COMMISSION r, -p WASHINGTON. D. C. 20555 k...../ April 19, 1985 MEMORANDUM FOR: Those on Attached List FROM: Dennis M. Crutchfield, Assistant Director for Safety Assessment Division of Licensing Thomas M. Novak, Assistant Director for Licensing Division of Licensing

SUBJECT:

FINAL DRAFT OF THE RIVER BEND UNIT I TECHNICAL SPlCIFICATIONS The attached final draft technical specifications for River Bend Unit 1 (enclosure 1) are.being forwarded to you at this time for review. We request that you review those sections which pertain to your particular area of responsibility and that the results of this review, identifying 11 the sections reviewed N ,:9 Group (TSRG)byMay/,beforwardedtotheTechnicalSpecificationReview , 1985. We are distributing these technical speci-fications at the NRR branch level, however, we request that the responses be consolidated, reviewed and returned at the Assistant Director level. By issuing these technical specifications in the final draft fem at this time without benefit of a fomal proof and review period between the second draft and the final draft, we are making a significant deviation from our normal technical specification preparation process. This deviation is being made in the interest of expediting the review process so as not to unneces-sarily delay the planned plant startup date of some time in June 1985. It is important to note, however, that even though we are skipping one of the steps in the preparation process we are not skipping any of the steps in our independent review and certification process to assure the safety adequacy of the technical specifications. These steps, such as, the NRC Regional review, the internal NRC technical branch reviews, the independent NRC consultant review, ard the applicants certification of the correctness of the technical specifications will be performed as shown on the enclosed marked up schedule for River Bend (enclosure 2). i This is a very ambitious schedule we will be working to and will require the complete cooperation of all the parties involved. The schedule has been reviewed by both the NRC and applicant's management and has been established as the goal both organizations will be striving to achieve. ) k )

. April 19, 1985 In making judgenents about the correctness or adequacy of these technical specifications for River Bend you should be cuided by the principles of NRR Office letter No. 38. Deviations from the (CE) STS should not be proposed or accepted by the staff or applicant unless they are: (1) necessary because of unique design features or unique organization characteristics, or (2) represent a significant improvement over the STS which should be included in the next revision to the STS and do not represent a change in generic reouirements which must be reviewed prior to implementation by CRGR. Deviations from the STS which have merit but are generic and require CRGR review should not be proposed at this time for River Bend. Instead they should be processed thru CRGR as a revision to the STS which can later be applied to River Bend at the licensee's request or as a backfit by the staff. Those generic changes involving an iminediate safety concern should, however, not be delayed for CRGR review. Any such cases should be highlighted for expedited action by DL and other appropriate NRC Divisions. Mr. Dean Houston, hf TSRG will be available during the final review period to answer ary questions which arise. He is located in Room 521, of the Phillips Building and his telephone number is 49-28933. Even if you have no conunents and are in agreement with the technical specifications content in your area of revie>.:, it is requested that a written response to that effect identifying those sections of the technical specifications reviewed be provided by the above specified date. Dennis M. ru ch i d, As 1stant Director for Safety Assessment Division of Licensing Thomas M. Novak, Assistant Director for Licensing Division of Licensing

Enclosures:

1. River Bend Nuclear Power Plant, Unit 1 Technical Specifications 2. River Bend marked up schedule cc: w/o enclosure see next page.

t April 19, 1985 CC: W/o enclosure H. Denton H. Thompson T. Speis J. Knight R. Bernero W. Russell G. Lainas F. Schroeder F. Rowsome W. Johnston R. Houston L. Rubenstein D. Muller R. Bosnak D. Beckhan ~

4 Distribution for River Bend Unit 1 Date: April 19,1985 ATTACHED LIST Al Schwencer, Chief Olan D. Parr, Chief Licensing Branch No. 2, DL Auxiliary Systems Branch, DSI Gary Holahan, Chief William P. Gannill, Chief Operating Reactors Assessment Meteorology and Effluent Branch, DL Treatment Branch, DSI B. D. Liaw, Chief Lewis G. Hulman, Chief Materials Engineering Branch, CE Accident Evaluation Branch, DSI Victor Benaroya, Chief Frank Congel, Chief Chenical Engineering Branch, DE , Radiological Assessment Branch, DSI Vincent Noonan, Chief William Regan, Acting Chief Equipment Qualification Branch, DE Human Factors Engineering Branch, DHFS Robert E. Jackson, Chief Dennis Ziemann, Chief Geosciences Branch, DE Procedures & Systems Review Branch, DHFS George Lear, Chief Robert D. Martin Structural & Geotechnical Reoional Administrator Engineering Branch, DE Region IV Ronald L. Ballerd, Chief John Jaudon Environnental & Hydrologic Senior Resident Inspector Engineering Branch, DE Region IV William H. Regan, Chief Harold R. Booher, Chief Site Analysis Branch, DE License Qualifications Branch, DHFS Frank C. Cherny, Acting Chief Mechanical Engineering Branch, DE Brian W. Sheron, Chief Reactor Systems Branch, DSI Faust Rosa, Chief G. Ted Ankrum, Chief Instrumentation & Control Quality Assurance Branch, I&E Systems Branch, DSI Walter R. Butler, Chief Steve Stern, Project Manager Containment Systems Branch, DSI Licensing Branch No. 2 DL M. I. Srinivasan, Chief Applicant: (3) Power Systems Branch, DSI Carl Berlinger, Chief Core Performance Branch, DSI l f

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