ML20132D021
| ML20132D021 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 05/13/1985 |
| From: | Beckham D Office of Nuclear Reactor Regulation |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20132C450 | List: |
| References | |
| FOIA-85-511 NUDOCS 8505220304 | |
| Download: ML20132D021 (10) | |
Text
l Nay 85 DISTRIBUTION:
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Central Files LQB Reading DHFS Reading - 2 H. Booher L N rocker" D. Ziemann
!>9 UN MEMORANDUM FOR: Dennis M. Crutchfield, Assistant Director for Safety Assessment Division of Licensing Thomas M. Novak, Assistant Director for Licensing Division of Licensing FROM:
Don H. Beckham, Acting Deputy Director Division of Human Factors Safety
SUBJECT:
REVIEW OF RIVER BEND TECHNICAL SPECIFICATIONS DHFS has reviewed Section 3/4.10 and Sections 6.1 through 6.8.3 of the final draft Technical Specifications for River Bend Unit 1.
Our comments are provided in Enclosure 1. is a copy of the pages from the draft Technical Specifications that we recommend should be changed, with the changes noted.
Subject to inclusion of the corrections noted, DHFS concurs with issuance of the Technical Specifications for River Bend Unit 1.
Or1GE-1le. -e57TILL"-'3.}gg,L n[ Don H. Beckham, Acting Deputy Director Division of Human Factors Safety cc:
E. Butcher LPC4/ RIVER BEND TECH SPEC
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1.
Section 6.1.2 - The words in lines 1 and 2 of this section which read "or during his absence from the control room, a designated individual" should be enclosed in parentheses.
Reason: To be consistent with the Standard Technical Specifications.
2.
Section 6.2.2.a - The words "on duty" in the first line should be hyphenated.
Reason: To be grammatically correct and to be consistent with the Standard Technical Specifications.
3.
Section 6.2.2.f - The words " health physicists" in lines 3 and 4 should be deleted and replaced with the words " radiation protection technicians."
Reason: To be consistent with the applicants' title for these individuals, as used in Section 6.2.2.c and in Figure 6.2.2.-l.
4.
Section 6.2.3.2 - Change the final clause in this section to read, "at least 1 year of which experience shall be in the nuclear field."
Reason: To improve the grammar and to be consistent with the wording of the Standard Technical Specifications.
2 5.
Section 6.4.1 - Insert a comma in the second line after the words Manager-Administration.
Reason: To be granratically correct and to be consistent with the Standard Technical Specifications.
6.
Section 6.5.1.6.e - Insert the words "Vice President - RBNG and the" in the last line between the words "the" and " Nuclear."
Reason: We have customarily required these FRC investigation reports to be furnished to the utility individual at the level of the Vice President - RBNG. Such a change also would make this section consistent with the wording of the Standard Technical Specifications.
7.
Section 6.3.5.7 - Change the lead words of this section to read, "The l
NRB shall be responsible for the review of:"
Reason: The NRB need not itself perform the reviews. The revised wording is consistent with the Standard Technical Specifications.
8.
Section 6.6 - Change the title of this section to read " Reportable Event Action."
Reason: To be consistent with the Standard Technical Specifications.
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3 6.0 ADMINISTRATIVE CONTROLS 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 Shif t Supervisor (or during his absence from the control room, a X
A management directiv)e to this effect, signed by the Senior Vice President
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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 6.2.2 The unit organization shall be as showr on Figure 6.2.2-1 and:
Each on,-duty shift shall be composed.mf at least the minimum shift X
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; c.
A Radiation Protection Technician
- shall be on site when fuel is'in the reactor; d.
All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; e.
A site fire brigade of at least five members shall be maintained on site at all times". The fire brigade shall not include the Shi't 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 "Tne Rac1ation Protection Technician and fire brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in orcer to accommodate unexpected absence, provided immediate action is taken to fill the required positions.
RIVER BEND - UNIT 1 6-1
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ADMINISTRATIVE CONTROLS km i
UNIT STAFF (Continued) f.
Administrative procedures shall be developed and implemented to limit radkfien pftfech'en the workino hours of unit staff who perform safety-related functions rgg n kiens,
(e.g., licensed Senior Operators, licensed operators,-td th ;S ;:= -r-y, 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 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
2.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time.
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3.
A break of at least eight hours should be allowed between work periods, including shif t 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 EEND - UNIT 1 6-2 IO E
FINAL DER ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) l FUNCTION 6.2.3.1 The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sou ces 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 proceduras, equipment modifications,
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maintenance activities, operations activities, or other means of improving unit safety to the Vice President - Safety and Environment.
COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time of wMeq engineers located onsite.
Each shall have a bachelor's degree in engineering tor related science and at least 2 years professional level experience in his~[sballbe 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 forwarded each calendar s!onth 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 Shif t 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 instrumentation and controls in the control room.
CK For the dual role position shown in Tablea6.2.2-1, the Shift Technical Advisor shall have a bachelor's degree or shall have completed all technical courses required for the degree in a scientific or engineering discipline and shall have received all of the training for the normal STA position described above.
"Not responsible for sign-off function.
RIVER BEND - UNIT 1 6-6 APR 2 61965
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FINAL MMT ADMis1STRATIVE 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 inclucing no more than two alf.ernates, t TMs go.// he realce / /c thru me ktr> if h sire d.
RESPONSIBILITIES 6.5.1.6 The FRC shall be responsible for:
Review of all plant general administrative procedures and changes a.
thereto; Review of all proposed tests and experiments that affect nuclear safety; b.
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;
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e.
Investigation of all violations of the Technical Specifications, (sq e. J N.
includinc the preparation and forwardina of rep rts covering evaluation and recommencations to prevent recurrence, to the Nuclear Review Board;
-f.
Review of all REPORTABLE EVENT 5;
,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, NRB 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 writin) 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 APR 2 61985
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 respen:,ible for the review of.*
6.5.3.7 The NRB shall,ress_er, 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 procedures, 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 Technic'al 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 on structures, systems, or components that could affect nuclear safety; and 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 APR 2 61985
i FINAL. DRKdd7 ADMINISTRATIVE CONTROLS RECORDS (Continued)
Minutes of each NRB meeting shall be prepared, approved, and forwarced 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 - R8NG 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 Ae riae 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
The Commission shJll 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 NRB 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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 Report shall be submitted to the Commission, c.
the NRB, and the Senior Vice President - RBNG within 14 days of the '
violation.
a d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintainea covering the activities referenced below:
hpg261356 RIVER BEND - UNIT 1 6-13
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FINAL DRAFT ADMINISTRATIVE CONTROLS
% bsec. Hon N. a.13. 3, 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 suoplier, 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 valuesoftheoperatingconditionsorcharacteristicsobtainedduringthetest 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 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 commence-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 si.artup test program, an.d resumption or commencement of commercial operation) 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 te 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 measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% ef 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.
"Tnis taoulation supplements the requirements of $20.407 of 10 CFR Part 20.
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RIVER BEND - UNIT 1 6-16 l
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- s UNITED STATES g
NUCLEAR REGULATORY COMMISSION y
REGION IV 811 RY AN PLAZA DRIVE. SulTE NIDO ARUNGTON. TEXAS 78011 HAY 101985 i
In Reply Refer To:
Docket:
50-458 Gulf States Utilities ATTN: William J. Cahill, Jr.
Senior Vice President River Bend Nuclear Group P. O. Box 2951 Beaumont, Texas 77704 Gentlemen:
The purpose of this letter is to request that you notify us when 90% of your surveillance procedures in support of Technical Specifications are approved for use.
Preliminary review of the results of the recent team inspection (April 29-May 3,1985) indicated that there was a shortfall in the preparation of procedures to implement Technical Specifications. We are still assessing the results of this inspection; however, preliminary review indicates that there were more than 300 open items identified by this inspection. The majority of these open items concern your procedures for implementing Technical Specifications. Additionally, some of the probleais found were with procedures which purportedly have been through your review process and were ready for use.
It is our experience that many operational problems experienced by newly licensed plants can be prevented by the careful preparation of procedures and a meticulous review of procedures prior to implementation.
The reinspection of Technical Specification implementing procedures is a large inspection effort. In order to plan this effectively, it is requested that you keep us closely advised of your progress toward the 901 completion point.
Sincerely, p
R. P. Denise, Director Division of Reactor Safety and Projects cc: (cont, on next page)
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t Gulf States Utilities Gulf States Utilities ATTN:
J. E. Booker, Manager-Engineering, Nuclear Fuels & Licensing P. O. Box 2951 Beaumont, Texas 77704 Louisiana State University, Government Documents Department Louisiana Radiation Control Program Director i
_ _. = _. _.. _.. _. -.. - _, _. _.. _
t MAY 101385 In Reply Refer To:
Docket:
50-458 Gulf States Utilities ATTN: William J. Cahill, Jr.
Senior Vice President River Bend Nuclear Group P. O. Box 2951 Beaumont, Texas 77704 Gentlemen:
The purpose of this letter is to request that you notify us when 90% of your surveillance procedures in support of Technical Specifications are approved for use.
Preliminary review of the results of the recent team inspection (April 29-May 3, 1985) indicated that there was a shortfall in the preparation of procedures to implement Technical Specifications. We are still assessing the results of this inspection; however, preliminary review indicates that there were more than 300 open items identified by this inspection. The majority of these open items concern your procedures for implementing Technical Specifications. Additionally, some of the problems found were with procedures which purportedly have been through your review process and were ready for use. It is our experience that many operational problems experienced by newly licensed plants can be prevented by the careful preparation of procedures and a meticulous review of procedures prior to implementation.
The reinspection of Technical Specification implementing procedures is a large inspection effort. In order to plan this effectively, it is requested that you keep us closely advised of your progress toward the 90% completion point.
Sincerely, o..~,,,.,
R. P. Denise, Director Division of Reactor Safety and Projects cc: (cont. on next pag RIV M
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t Gulf States Utilities Gulf States Utilities ATTN:
J. E. Booker, Manager-Engineering, Nuclear Fuels & Licensing P. O. Box 2951 Beaumont, Texas 77704 Louisiana State University, Government Documents Department Louisiana Radiation Control Program Director bec:
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R. D. Martin, RA Rssident inspector R. P. Denise, DRSP Section Chief, RPB1/A D. Weiss, LFMB (AR-2015)
EP&RPB' RIV File H. Denton, NRR H. Thompson, NRR S. Stern, NRR 4
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MAY 2 1985 Docket No. 50-458 Mr. William J. Cahill, Jr.
Senior Vice President i
I River Bend Nuclear Group Gulf States Utilities Company Post Office Box 2951 Beaumont, Texas 77704 ATTN: Mr. J, E. Booker
Dear Mr. Cahill:
SUBJECT:
RIVER BEND-STATION UNIT 1 TECHNICAL SPECIFICATIONS In your application for an operating license, you included proposed technical specifications.
During the course of our review of your aoplication, we have worked with you on these Technical Specifications to develop the proper wording and substance.
{
l Enclosed is a final draft of the River Bend Station Unft 1 Technical Specifications.
Please review the enclosed draft and submit, in a timely manner to support license issuance, a certification under oath and affinnation that, to the best l
of your knowledge, the erciosed draft accurately reflects the plant FSAR, the staff's SER, and the as-built configuration of the plant. In addition, we request that you describe in your response, in some detail, the process and resources used to accomplish this review.
Consistant with the accelerated review schedule for River Bend Station Technical Specification, please provide your certified submittal by May 13, 1985. Should you have any questions regarding this matter, please contact the NRC, Project Manager, Stephen Stern at (301) 492-8348.
Sincerely.
OriDimi s!rmo by:
Thomas M. Novak, Assistant Director 7).'
-gA Ii for Licensing h-(A 0
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Division of Licensing l