ML20215H907
| ML20215H907 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 06/18/1987 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20215H897 | List: |
| References | |
| NUDOCS 8706240258 | |
| Download: ML20215H907 (24) | |
Text
4 6.0 ADMINISTRATIVE CONTROLS 4
6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and i
shall delegate in writing the succession to this responsibility during his absence.
i 6.1.2 The Shift Supervisor (or during his absence from the control room, a designated individual) shall be responsible for the control room command function.
A management directive to this effect, signed by the Senior Vice President -
River Bend Nuclear Group, shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION 0FFSITE 6.2.1 'The offsite organization for unit management and technical support shall be as shown ea Tig..
0.2.1 1. lin Chapter 13 of the current Safety Analysis Report.l l
9 UNIT STAFF in Chapter 13 of the current Safety Analysis Reportl 6.2.2 The unit organization sla11 be as shown en T's..
- 0..2. hand:
l a.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1; b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
In addition while the unit is in OPERATIONAL i
s CONDITION 1, 2 or 3, at least one licensed Senior Operator shall be in the control room; l
c.
A Radiation Protection Technician
- shall be on site when fuel is in the reactor, i
1 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; A site fire brigade of at least five members shall be maintained on m
e.
. mpg site at all times *. The fire brigade shall not include the Shift pga.
Supervisor, the Shift Technical Advisor, the Control Operating Foreman, nor the two othat members of the minimum shift crew necessary for saf-ooM shutdown of the unit and any personnel required for other essential functions during a fire emergency; and "The Radiation Protection Technician and fire brigade composition may be less than g<
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 order 4
.Rg to accommodate unexpected absence, provided immediate action is taken to fill maa.
the required positions.
RIVER BEND - UNIT 1 6-1
i ADMINISTRATIVE CONTROLS UNIT' STAFF (Continued) f.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions (e.g., licensed Senior Operators, licensed Operators, radiation pro-tection technicians, 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 42-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 refuel-ing, 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 l
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.
3.
A break of at least eight hours should bg 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
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i TABLE 6.2.2-1 MINIMUM SHIFT CREW COMPOSITION SINGLE UNIT FACILITY POSITION NUMBER OF INDIVIDUALS 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 ifcense 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 room 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.
RIVER BEND - UNIT 1 6-5
I ADMINISTRATIVE CONTROLS l
6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)
FUNCTION 1
i 6.2.3.1 The ISEG shall function to examine unit 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 Vin Prn idn t - O f;t3 nd Enitenment.IManager-River Bend Oversight.]
l 9
COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time cngineers located onsite.
Each shall have a bachelor's degree in engineering er related science and at least 2 years professional level experience in his field, of.which at least 1 year experience shall be in the nuclear field.
RESPONSIBILITIES I
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 l
6.2.3.4 Records of activities performed by the ISEG shall be prepared, main-tained, and forwarded each calendar month to the Vin Finidst - Of;ti end-m Entren;;t.[Mansger-River Bend Oversight.l l
l 6.2.4 SHIFT TECHNICAL ADVISOR Idedicatedl 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, cnd 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, J
including the capabilities of instrumentation and controls in the control room.
For the dual role position shown in Table 6.2.2-1, the Shift Technical Advisor shall hav) a bachelor's degree ;r ;t;11 he ; :npiet;d eli tnhnini nur;n rq ; ired fu tt; dq rn in a scientific or engineering discipline.and shall have received all of the training for the normal STA position described above.
lor a Professional Engineer's Licensel "Not responsible for sign-off function.
)
RIVER BEND - UNIT 1 6-6
1 1
l
+
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 Reguletory 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 Director - Nuclear Training and 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 licensees, 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 l
related to nuclear safety.
COMPOSITION 6.5.1.2 The FRC shall be composed of the:
Chairman:
Assistant Plant Manager-Technical Services tand Radwast ei Member:
Assistant Plant Manager-0perationsfl'ed e;te and CM;i;try Member:
Assistant Plant Manager-Maintenance r.d ".:t:ri:1 3
Member:
Operations Supervisor j
Member:
Supervisor-Radiological Program
)
Member:
Reactor Engineering Supervisor Member:
Control Systems Supervisor j
Nember:
Chemistry Supervisori ALTERNATES Nember:
Process systems supervisori f.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
j t
i l
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 four members including no more than two alternates.
i RESPONSIBILITIES 6.5.1.6 The FRC shall be responsible for:
a.
Review of all plant general administrative procedures and changes thereto; 4
b.
Review of all proposed tests and experiments that affect nuclear safety; c.
Review of all proposed changes to Appendix A Technical Specifications; d.
Review of all proposed changes or modifications to structures, compo-nents, systems or equipment that affect nuclear safety; I
e.
Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to thegVice President - RBNG l
1 and the Nuclear Review Board; 15eniori 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 that require written response, QA audits / surveillance findings of operating and maintenance activities, NRB audit results, and Ameri-can Nuclear Insurer (ANI) iisspection results; h.
Perfomance of special reviews, investigations, or analyses and reports thereon as requested by the Plant Manager or the Nuclear Review Board; 1.
Review of initial start-up testing phase start-up procedures and revisions; and i
,j.
Review of the Emergency Plan and implementation procedures at least once per 12 months and all proposed changes thereto.
6.5.1.7 The FRC shall:
a.
Recommend in writing to the Plant Manager approval or disapproval of 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 SpecificatTon 6.5.1.6.a. through e. constitutes an unreviewed safety question.
g c.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the(Vice President -
l 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
i
\\
ADMINISTRATIVE CONTROLS RECORDS
{
i 6.5.1.8 The FRC shall maintain written minutes of each FRC meeting that, at a 1
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 CGNTROL 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-fled individual / organization.
Each such procedure, and changes thereto, shall be reviewed by an individual / group other than the individual / group that pre-pared the procedure, or changes thereto, but who may be from the same organiza-
{
tion as the individual / group that prepared the procedure.
Each such procedure 1
and program, or changes thereto, shall be approved, prior to implementation, by the Plant Manager or one of the Assistant Plant Managers or the Supervisor -
Radiological Programs, with the exception of the Emergency Plan and implement-ing procedures which shall be approved by the Manager - Administration, Plant I
Manager and Vice President - RBNG.
l {
g 15eniori I
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 shall be performed in accordance with administrative procedures.
Each such review shall include a deters.ination 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 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 and recommended changes shall be approved in accordance 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 Reccrds 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 (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
l ADMINISTRATIVE CONTROLS FUNCTION (Continued) a.
Nuclear power plant operations, b.
Nuclear engineering, c.
Chemistry and radiochemistry, d.
Metallurgy, e.
Instrumentation and control, f.
Radiological safety, g.
Mechanical and electrical engineering, h.
Quality assurance practices, 1.
Licensing and regulatory affairs, J.
Training.
The NRB shall report to and advise the Senior Vice President - RBNG on those 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:
IManager-River Bend Oversight 1 Chairman:
t';;; Pr;;id;nt 0;f;;:, ;nd Crv'r;r ;n,t Member and Vice "i;; Tr ;id;nt
- ,1; IManager-Quality Assurancel Chairman N
Member:
Manager - Administration
";;b;..
Ex;;;tiv; "!;e Pr.;ide..; : te...;; Affe!.....d P..d.;;...
l Member:
Manager-Design Engineering, Technical Services Department Member:
";n;;;r-In;in;;r'ne, 9;;1;m F-iManager-Engineering) y;;;;, ;7,3 ;s;;;;13; Member:
Plant Manager
- and Radwast el e
Member:
Assistant Plant Manager-0perations,e ;d.;;;; and Or,;;;;tr, A
Member:
";;;;;r ^;;lita ".;;;r;n;; IDirector-Design Engineering l l
Member:
Director-Nuclear Licensing Member:
Oir;;ter M;;1;;r P!;nt ing'n;;r'n;
- ~'~10utage Manager l Shnd>>P:
Oir;;t;r M;;l;;r I;;1; 0;;ign nd 0;f;t3.",n;1y;i; IMember:
Director-Joint Ownership Participation l i
ALTERNATES 1
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.
l l
RIVER BEND - UNIT 1 6-10
l a
i ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.3.5 The NR8 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.
000 RUM 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 NR8 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 6.5.3.7 The NR8 shall be responsible for the review of:
a.
The safety evaluations for (1) changes to procedures, equipment, or j
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; c.
Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; d.
Proposed changes to Technical Specifications or this Operating License; 1
e.
Violations of codes, regulations, orders, Technical Specifications, 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 1.
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
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 months; b.
The perfonnance, 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 B,10 CFR Part 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; 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 i
g.
Any other area of unit operation considered appropriate by the NRB, Plant Manager or the Senior Vice President - RBNG.
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.
i
..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 least once per 24 months.
1.
The PROCESS CONTROL PROGRAM and implementing procedures for solidifi-cation of radioactive wastes, at least once per 24 months.
m.
The performance of activities by the Quality Assurance Program for effluent and environmental monitoring, at least once per 12 months.
i
' RECORDS i
6.5.3.9 Records of NRB activities shall be prepared, approved, and distributed i
cs indicated below:
l 1
RIVER BEND - UNIT 1 6-12 l
i
I 4
ADMINISTRATIVE CONTROLS RECORDS (Continued) a.
Minutes of each NRB meeting shall be prepared, approved, and forwarded 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.
c.
Audit reports encompassed by Specification 6.5.3.8 shall-be forwarded 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 ACTION t
l 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.73 and b.
Each REPORTABLE EVENT shall be reviewed by.the FRC and the results l
of this review shall be submitted to the NRB and the Plant Manager.
l 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. 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.
d.
Critical operation of the unit shall not be resumed until authorized I
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 a
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 supplements thereto.
i c.
Refueling operations, j
d.
Surveillance and test activities of safety-related equipment.
e.
Security Plan implementation.
i f.
Emergency Plan implementation.
g.
Fire Protection Program implementation.
h.
Process Control Program implementation.
1.
Offsite Dose Calculation Manual implementation.
j.
Quality Assurance Program for effluent and environmental monitoring.
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 Specificatiot,6.8.1 may be made pro-vided:
a.
The intent of the original procedure is not altered; b.
The change is approved by two members of the plant management staff, j
at least one of whom holds a Senior Operator license on the unit affected; and c.
The change is documented, reviewed by the FRC as required by Specifi-
[
cation 6.5.1.6, and approved in accordance with Specification 6.5.2.1 within 14 days of implementation.
6.8.4 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment l
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 practicable levels. The l
systems include the HPCS, LPCS, RHR, RCIC, process sampling, and standby l
gas treatment systems. The program shall include the following:
1.
Preventive maintenance and periodic visual inspection requirements, and RIVER BEND - UNIT 1 6-14
e i
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 2.
Integrated leak test requirements for each system, at refueling cycle intervals or more frequently, b.
In-Plant Radiation Monitorina 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 Samplina A program 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 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.
Biofoulina Prevention and Detection A program, approved by the NRC Staff prior to introduction of river water to the systems, which will include the procedures to prevent biofouling of safety-related equipment, to assure detection of Corbicula in the intake embayment and the Mississippi River at the River Bend Station site, and to monitor and survey safety-related equipment to de-tect biofouling.
Changes to this program will be submitted to and i
approved by the NRC (both the Region and NRR) prior to implementation.
~
6.9 REPORTING REQUIREMENTS U. S. Nuclear Regulatory Commission, Document Control Deck, Washington, DC 20555, with a copy to ROUTINE REPORTS the Regional Office of the NRC and a copy to the NRC Resident Inspector.
6.9.1 In addition to the applicable reportirg requirements of Title 10, code ofFederalRegulations,thefollowingreportsshallbesubmittedtothep;i;;;;
" i'n';tr;;;r ;f 0; ";;';;;l Off';; ef L = 0 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 l
ADMINISTRATIVE CONTROLS STARTUP REPORT (Continued) the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered tha nuclear, thermal, or hydraulic performance of the unit.
6.9.1.2 The startup report shall address each of the tests identified in Final Safety Analysis Report (Section 14.2.12.2) and shall include a descrip-tion of the measured values of the operating conditions or characteristics ebtained during the test program and a comparison of these values with design predictions
- and specifications.
Any corrective actions that were required to cbtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be in-cluded in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following comple-tion of the startur et program, (2) 90 days following resumption or commence-cent of commercial power operation, or (3) 9 months following initial criticality, whichever is earlbst.
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 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.
1 6.9.1.5 Reports required on an annual basis shall include:
a.
A tabulation on an annual basis of the number of station, utility, j
and other personnel (including contractors) receiving exposures greater j
than 100 arem/yr and their associated man-rem exposure according to i
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% 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 and a summary of SRV failures.
"This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.
RIVER BEND - UNIT 1 6-16
ADMINISTRATIVE CONTROL I
ANNUAL REPORTS (Continued)
C.
The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.5.
The following information shall be included:
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiofodine activity was reduced to less than limit.
Each re-cult should include date and time of sampling and the radiofodine concen-trations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the
{
first sample in which the limit was exceeded; (4) Graph of the I-131 con-centration and one other radioiodine isotope concentration in microcuries j
per gram as a function of time for the duration of the specific activity 1
above the steady-state level; and (5) The time deration when the specific activity of the primary coolant exceeded the radioiodine limit.
1 MONTHLY OPERATING REPORTS
{
6.9.1.6 Routine reports of operating statistics and shutdown experience, in-cluding documentation of all failures 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 following the calendar month ccvered 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 sebmitted prior to May 1 of each year.
The initial report shall be submitted prior to May 1 of the year fc11owing 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, including 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 analyses of 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 CALCU.LATION 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 RIVER BEND - UNIT 1 6-17 6,.e,--,m
-..---.-m
4 ADMINISTRATIVE CONTROLS
)
j ANNUAL-RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued).
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
- j covering all sampling locations hyed to a table giving distances and of rections from the centerline of the reactor plant; the results of licensee participation s
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 LLD required by Table 4.12.1-1 was not achievable.
SEMIANNUAL EFFLUENT RELEASE REPORT 6.9.1.8 Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within~60 days after January 1 and July 1 of each year.
The period of the first report shall begin with the 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, t
- 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.
For solid wastes, the format for
-Table 3 in Appedix B shall be supplemented with three additional categories:
class of~ solid wastes (as defined by 10 CFR Part 61), type of container (e.g.,
LSA, Type A,' Type 8, Large Quantity) and SOLIDIFICATION agent or absorbent (e.g., cement, urea formaldehyde).
The Semiannual Radioactive Effluent Release Repert 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 cf an hour-by-hour listing on magnetic tape of wind speed, wind direc-tion and atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmaspheric stability.** This same report shall include an assessment of the radiation doses due to the radinactive liqubi and gaseous effluents released from the unit or station daring the previous calendar year.
This same report shall also include an assessment of the radiation dose.s from radioactive liquid and gaseous effluents "One map shall cover stations naar the SITE BOUNDARY; a second shall include the more distant stations.
- 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 j.
NRC upon request.
i RIVER BEND - UNIT 1 6-18
l' f
' ADMINISTRATIVE CONTROLS SEMIANNUAL EFFLUENT RELEASE REPORT (Continued) to' MEMBERS OF THE PUBLIC'due to their activities inside the SITE BOUNDARY (Figure 5.1.3) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be in-cluded in these reports. The assessment of radiation doses shall be performed in accordance with the methodology and parameters of the 0FFSITE DOSE CALCULA-
' TION MANUAL (0DCM).
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 0F 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 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 reporting 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 U. 5. Nuclear Regulatory Commission, Document Control Desk, SPECIAL REPORTS Washington, DC 20555, with a copy to the Regional Office of the NRC and a copy to the NRC Resident Inspector, 6.9.2 'Special reports shall be submitted in the following manner:
E Special reports shall be submitted to the L ;'er.d fix' i t;;;;r ;f a.
th: 5;S::: Cff' s of th; 1"C within the time period specified for each report.
b.
Special reports in regard to Corbicula will be submitted to the NRC within 30 days of identification of infestation.
In accordance with the settlement agreement dated October 10, 1984, these reports shall describe the level of infestation, affected systems and measures taken to prevent further infestation.
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 years:
Records and logs of unit operation covering time interval at each a.
power level.
RIVER BEND - UNIT 1 6-19
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.y 1
l 1
Y
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CyADMINISTRATIVECONTROLS
]
t.
RECORD NETENTION (Continued)'
3 bl 3 Records and'1ogs of principal maintenance activities, inspections, i
repair, and replacement of principal items of equipment related to nuclear safety.
q
)
c.
All REPORTABLE EVENTS d.
Records of surveillance activities, inspections, and calibrations i
required by these Technical Specifications.
{
Records of changes made to the procedures required by Specification e.
- 6. 8.1.
f.4 [ Records of radioactive shipments.
c,;4 g'./ Qecords of sealed source and fission detector leak tests and results.
h.
Records of annual physical inventory of all sealed source material of record.
1.
Records of emergency drills and exercises.
s 6.10.3 The follwing records shall be retained for the duration of the unit Operating License:
Records and dtdwing changes reflecting unit design modifications made a.
to systems and equipment described in the Final Safety Analysis Report, b.
Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.
Records of radiation exposure for all individua's entering radiation c.
control areas.
d.
Records of gaseous and liquid radioactive material released to the environs.
e.
Records of transient or operational cycles for those unit components identified in Table 5.7.1-1.
f.
Records of reactor tests and experiments.
.,[
g.
Records of tra(ning and qualification for current members of the unit
- ?
staff.
- h.,, Records of inservice inspections performed pursuant to these Technical Specifications.
1.
Records of quality assurance activities required by the Operational
, Quality Assurance Manual that are not listed in Specification 6.10.1.
\\
k i
1
' RIVER M ND - UNIT 1 6-20
]
l ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) 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 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.
m.
. Records of analysis required by the Radiological Environmental Moni-toring Program that would permit evaluation of the accuracy of the analysis at a later date.
This should include procedures effective
'at the specified times and QA records showing that these procedures were followed.
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 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 mrem /hr shall be barricaded and conspicuously posted as a high radiation r ea, and entrance thereto shall be controlled by requiring issuance of a Radiation Wo.k 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.
A radiation monitoring device which continuously indicates the 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.
c.
An individual qualified in radiation protection procedures, with a radiation dose rate monitoring device, who is responsible for provid-ing positive control over the activities within the area and who shall perform periodic radiation surveillance at the frequency specified in the RWP by the Health Physicist.
" Radiation protection personnel or personnel escorted by radiation protection personnel shall be exempt from the RWP issuance requirement during the perfor-mance of their assigned duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.
RIVER BEND - UNIT 1 6-21
ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued).
6.12.2 In addition to the requirements of Specification 6.12.1, accessible areas with radiation levels such that a major portion of the body could receive in I hour a dose greater than 1000 arem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the adminis-trative control of the Control Operating Foreman on duty and/or the radiation protection supervision. Doors shall remain locked except during periods of access under an approved RWP that specifies the dose rate levels in the imme-diate work area and the maximum allowable stay time for individuals in that For accessible areas that are located within large areas, such as the area.
containment, where no enclosure exists for purposes of locking and no enclo-sure can be reasonably constructed around the individual areas, and within which radiation levels are such that a major portion of the body could receive-4 in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrem,* then that area shall be roped off and conspicuously posted, and a flashing light shall be activated as a warning device.
In Ifeu of the stay time specification of the RWP, continuous surveil-lance, direct or remote (such as use of closed circuit TV cameras), may be made by personnel qualified.in radiation protection procedures to provide positive exposure control over the activities within the area.
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 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 to Speci-fication 6.5.2.
i l
i
'Weasurement made at 5 18 inches from source of radioactivity.
RIVER BEND - UNIT 1 6-22
t ADMINISTRATIVE CONTROL 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 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 date box, together with appro-priate analyses or evaluations justifying the change (s);
b.
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and Documentation of the fact that the change has been reviewed 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.
6.15 MAJOR CHANGES TO RADIDACTIVE 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 of the change was reviewed and approved prsuant to Specification 6.5.2.
The discussion of each change shall contain:
I A summary of the evaluation that led to the determination that a.
the change could be made in accordance with 10 CFR Fort 50.59.
b.
Sufficiently 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; RIVER BEND - UNIT 1 6-23
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I i
l l
ADMINISTRATIVE CONTROL d.
An evaluation of the change, which shows (1) the predicted releases
-of radioactive materials in liquid and gaseous effluents and/or (2) quantity of solid waste, that differ from those previously predicted in the ifcense application and amendments thereto; 3
An evaluation of the change, which shows the expected maximum e.
i exposures, to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA i
and to the general population, that differ from those previously estimated in the ifcense 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.
4 RIVER BEND - UNIT 1 6-24