ML20237B875
| ML20237B875 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 12/09/1987 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237B876 | List: |
| References | |
| NUDOCS 8712170215 | |
| Download: ML20237B875 (10) | |
Text
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'o, UNITED STATES NUCLEAR REGULATORY COMMISSION g
E WASHINGTON, D. C. 20555
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GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.I7 License No. NPF-47 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has j
found that:
A.
The application for amendment filed by Gulf States Utilities Company, dated June 18, 1987 as supplemented July 31, 1987 and revised October 8, 1987, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I;
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)
B.
The facility will operate in conformity with the application, the
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provisions of the Act, and the regulations of the Commission; 4
C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l 8712170215 871209 i
PDR ADOCK 05000458 P
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1
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and
-Paragraph 2.C.-(2) of Facility Operating License No. NPF-47 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Arendment No.1/ and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in_the license. GSU shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION-llm ci 1-e w
Jose A. Calvo, Cirector-Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Cete of Issuence:
December 9,1987
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ATTACHMENT"T'O LICENSE AMENDMENT NO. 17' FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following page of the Appendix "A" Technical Specifications with-the enclosed page..The, revised page is. identified by Amendment number and contains a vertical line indicating.the area of change.
Overleaf page provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 6-1 6-1 6-2 6-2 6-3 6-3
~
6-4 6-4 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6-10 6-10 6-15 6-15 6-19 6-19
6.0 ADMINISTRATIVE CONTROLS
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6.1 RESPONSIBILITY 1
6.1.1 The Plant Manager shall be responsible for overall unit operation and j
shall delegate in writing the succession to this responsibility during his j
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 l
I 0FFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown in Chapter 13 of the current Safety Analysis Report.
l UNIT STAFF 6.2.2 The unit organization shall be as shown in Chapter 13 of the current Safety Analysis Report and:
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 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; j
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 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 Radiation 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 order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.
RIVER BEND - UNIT 1 6-1 Amendment No. 17 l
CNAIRMAN OF THE BOARD emmuuma SENIOR MCE PRESIDENT RBNG MANAGER MANA M PLANT MANAGER WANAGER RIVER BEND PROJECT ENQNEERING ADMINISTRATION WANAGER OVERSGHT MANAGEMENT I
I SUPERMSOR l
INDEPENDENT DIRECTOR DIRECTOR SUPERVISOR DIRECTOR SAFETY RIVER BEND MANAGEMENT l
ENQNEERING NUCLEAR ADMINISTRA110N TRAINING ENQNEERING PROJECTS SYSTEMS l
GROUP l
I DIRECTOR DIRECTOR l
SUPERVISOR SUPERVISOR PLANT MATERIALS EHQNEERING EMERGENCY OVERSIGHT MANAGEMENT l
ANALYSS PLANNING 1
I SUPERMSOR DIRECTOR SUPERMSOR NUCLEAR OUTAGE NUCLEAR l
MANAGER STATION UCENSNG AgALygg l
SECURITY m.m l
i l
MANAGER SUPERMSOR OUAUTY PLANNING &
l DIRECTOR SUPERMSOR ASSURANCE SCHEDUUNG l
DESGN ADMINISTRATIVE ENQNEERING SERMCES 1
m-a mm I
DIRECTOR SUPERMSOR DIRECTOR SUPERMSOR NUC11AR L"""
rie mMRmMmTAt l QUAUTY SERMCES FUELS ENQNEERING SERMCES
.mmmuummmmmmu Reports odeninistrettwly to the Monoger-Engineering.
OP R ONS t ',
nsible for day-to-doy engineering suppoM QA unamusumanumme FIGURE 6.2.1-1 RIVER BEND STAllON ORGANIZATION RIVER BEND - UNIT 1 6-3 Amendment No. 17
TABLE 6.2.2-1 MINIMUM SHIFT CREW COMPOSITION SINGLE UNIT FACILITY l
l POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION l
CONDITION 1, 2, or 3 CONDITION 4 or 5 I
SS 1
1 SRO 1
None RO 2
1 A0 2
1 STA*
1 None TABLE NOTATION SS - Shif t 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 i
- The Shif t Technical Advisor (STA) position may be filled by an on-shif t 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 shif t 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 Shif t 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
ADMINISTRATIVE CONTROLS 1
6.3 UNIT STAFF QUALIFICATIONS l
6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-I tions of ANSI /ANS 3.1-1978 for comparable positions, except for the Director-l 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
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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 /
i ANS 3.1-1978 and Appendix A of 10 CFR Part 55 and the supplemental requirements i
specified in Secticas 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 i
6.5.1.1 The FRC shall function to advise the Plant Manager on all matters related to nuclear safety.
COMPOSITION l
l
- 6. 5.1. 2 The FRC shall be composed of the:
Chai rman:
Assistant Plant Manager-Technical Services Member:
Assistant Plant Manager-Operations and Radwaste Member:
Assistant Plant Manager-Maintenance Member:
Operations Supervisor Member:
Director-Radiological Program
(
Member:
Reactor Engineering Supervisor Member:
Control Systems Supervisor Member:
Chemistry Supervisor Member:
Process Systems 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 Amendment No. 17 1
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 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 and program, or changes thereto, shall be approved, prior to implementation, by the Plant Manager or one of the Assistant Plant Managers or the Director -
l Radiological Programs, with the exception of the Emergency Plan and implement-ing procedures which shall be approved by the Manager - Administration, Plant Manager and Senior Vice President - RBNG.
l 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 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 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 5.5.2.1.
6.5.2.6 Records 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 Amendment No. 17
t 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 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 program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulate 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.
Biofouling 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 approved by the NRC (both the Region and NRR) prior to implementation.
6.9 REPORTING REQUIREMENTS 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 U.S.
Nuclear Regulatory Commission, Document Control Desk, Washington, DC 20555, with a copy to the Regional Office of the NRC and a copy to the NRC Resident Inspector, 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 Amendment No. 17
ADMINISTRATIVE CONTROLS SEMIANNUAL EFFLUENT RELEASE REPORT (Continued) to MEMBERS OF THE PUBLIC due to their activities inside the SITE B0UNDARY (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 p'arameters 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 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 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 SPECIAL REPORTS 6.9.2 Special reports shall be submitted in the following manner:
a.
Special reports shall be submitted to the U.S. Nuclear Regulatory Conroission, Document Control Desk, Washington, DC 20555, with a copy to the Regional Office of the NRC and a copy to the NRC Resi-dent inspector, 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 l
l the settlement agreement dated October 10, 1984, these reports shall j
describe the level of infestation, affected systems and measures taken to prevent further infestation.
6.10 RECORD RETENTION j
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:
a.
Records and logs of unit operation covering time interval at each power level.
RIVER BEND - UNIT 1 6-19 Amendment No.I7
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