ML20153D455
| ML20153D455 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/29/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20153D459 | List: |
| References | |
| NUDOCS 8809020210 | |
| Download: ML20153D455 (12) | |
Text
....
[jI h,
UNITED STATES
+
g NUCLEAR REGULATORY COMMISSION 5
- l WASHINGTON,0. C. 2f 555 GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION. UNIT 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 27 License No. NPF-47 l
1.
The Nuclear Regulatory Comission (tte Comission) has found that:
A.
The application for amendment by Gulf States Utilities Cor.pany (thelicensee)datedJune 21, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comissien's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in con (annity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance:
(1) that the activities authorized by this amendnent can be conducted eithout eidangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comen 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 Comission's regulations and all applicable requirements have been satisfied.
$$f0$$[cc0bb
$8 P
2.
Accordingly, the license is amended by changes to the Technical Specifications 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 Specificatiens contained in Appendix A, as revised through Amendment No. 27 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
?/ m ' 4. A tyv Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 29, 1988
ATTACHMENT TO LICENSE AMENDMENT NO. 27 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contains vertical lines indicating the area of change. Overleaf pages provided to maintain document completeness.
REMOVE PAGES INSERT PAGES xxii xxii 6-1 6-1 6-la 6-2 6-2 6-3 6-3 6-4 6-4 6-17 6-17 t
i P
t n
i
,~,-__ -. _ _ _ _ _ _ _.. _ _, _ _,, _ _. - _... _ _, _ _ _ _ _ _ _ _ -. _
~
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.13 PROCESS CONTROL PROGRAM (PCP)................................
6-22 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM).......................
6-23 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS AND SOLID WASTE TREATMENT SYSTEM5............................................
6-23 1
1 i
t l
l RIVER BEND - UNIT 1 xxi
INDEX LIST OF FIGURES FIGURE TITLE PAGE 3.2.1-1 Maximum Average Planar Linear Heat Generation Rate (BP85RB094)...................................
3/4 2-2 3.2.1-2 Maximum Average Planar Linear Heat Generation Rate (BP85RB163)....................................
3/4 2-3 3.2.1-3 Maximum Averaga Planar Linear Heat Generation Rate (BP85RB248).....................................
3/4 2-4 3.2.1-4 Maximum Average Planar Linear Heat Generation Rate (BP85RB278).....................................
3/4 2-5 3.2.1-5 Maximum Average Planar Linear Heat Generation Rate (BP85RB299).....................................
3/4 2-6 3.2.1-6 Maximum Average Planar Linear Heat Generatiun Rate (BP85RB305).....................................
3/4 2-6A 3.2.3-1 NCPR..............................................
3/4 2-9 f
3.2.3-2 MCPR..............................................
3/4 2-10 p
3.4.1.1-1 Thermal Power versus Core Flow.....................
3/4 4-3 3.4.6.1-1 Minimum Temperature Required Versus Reactor Pressure...........................................
3/4 4-24 4.7.4-1 Sample Plan for Snubber Functional Test............
3/4 7-15 B 3/4 2.3-1 Power Flow Operating Map...........................
B 3/4 2-6 B 3/4 3-1 Reactor Vessel Water Leve1.........................
B 3/4 3-8 B 3/4.4.6-1 Fast Neutron Fluence (E>l MeV) at 1/4 T as a Function of Service Life...........................
B 3/4 4-8 5.1.1-1 Exclusion Area.....................................
5-2 5.1.2-1 Low Population Zone................................
5-3 5.1.3-1 Map Defining Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents.......
5-4 RIVER BEND - UNIT 1 xxii Amendment No. I3,27
' i, 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 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 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.
The onsite organizations shall include the positions for activities affecting the safety of the nuclear power plant, a.
Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented in Chapter 13 of the Updated Safety Analysis Report, b.
The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant, c.
The Senior Vice President - RBNG shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintain-ing, and providing technical support to the plant to ensure nuclear
- safety, d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 UNIT STAFF a.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1; RIVER BEND - UNIT 1 6-1 Amendment No. 27
- 6. 0 ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) 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 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 otner essential functions during a fire emergency; and 4
"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-la Amendment No.27
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-tactiontechnicians,auxiliaryoperators,andkeymaIntenance personnel).
Adequate shift coverage shall be maintained without routine heavy use of overtime.
The objective shall be to have operating personnel l
work a nominal 42-hour week while the unit is operating.
However, in the event that unforeseen problems require substantial amounts of overaime to be used, or during extended periods of shutdown for refuel-i ing, major m'tintenance, or major unit modifications, on a temporary basis the following guidelines shall be followed:
l 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 /> I
l 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.
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 Assistarit Plant Managers or the Director-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 bc 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.
g.
The Operations Supervisor, Assistant Operations Supervisor, Shift Supervisor and the Control Operating Foreman, as specified in Chapter 13 of the Updated Safety Analysis Report, shall hold a senior reactor operator license. The Nuclear Control Operators shall hold, as a minimum, a reactor operator license as specified in Chaptor 13 of the Updated Safety Analysis Report.
RIVER BEND - UNIT 1 6-2 Amendment No. 27, 27
o l
l FIGURE 6.2.1-1 This figure has been deleted RIVER BEND - UNIT 1 63 Amendment No. 27,27
3 l
FIGURE 6.2.2 1 This figure has been deleted 1
i I
RIVER BEND - UNIT 1 6-4 Amendment No.17,27
\\
t ADMINISTRATIVE CONTROL 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 radioiodine activity was reduced to less than limit.
Each re-sult should include date and time of sampling and the radiciodine 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 per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.
MONTHLY OPERATING REPORTS 6.9.1.6 Routine reports of operating statistics and shutdown experience, in-ciuding documentation of all failures to the main steam system safety / relief valves, shall be submitted on a monthly basis no later than the 15th of each l
month following the calendar month covered by the report.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.7 Routine Annual Radiological Environmental Operating Reports cove.ing the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
The initial report shall be submitted prior to May 1 of the year following initial criticality.
The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, 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 CALCULATION MANUAL, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Branch Technical Position, Revision 1, November 1979.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining RIVER BEND - UNIT 1 6-17 Amendment No.27
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued) l 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 l
radiological environmental monitoring program; at least two legible maps
- covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor plant; the results of Ifcensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3; discussion of all deviations from the Sampling Schedule of Table 4.12.1-1; and i
discussion of all analyses in which the LLD required by Table 4.12.1-1 was not i
achievable.
l SEMIANNUAL EFFLUENT RELEASE REPORT i
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 af ter January 1 and July 1 of each year.
The period of the first report shall begin with the date of initial criticality.
The Sesiannual Radioactive Effluent Release Reports shall include a summary of l
the quantities of radioactive ifquid and gaseous effluents and solid waste released from the facility as outlined in Regulatory Guide 1.21 "Measuring, j
Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear i'
Power Plants " Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix 8 thereof.
For solid wastes, the femat for Table 3 la Appedix 8 shall be supplemented with three additional categories:
class of solid wastes (as defined by 10 CFR Part 61), type of container (e.g.,
i LSA, Type A, Type B, Large Quantity) and SOLIDIFICATION agent or absorbent j
(e.g., cement, urea fonnaldehyde),
i i
The Seelannual Radioactive Effluent Release Report to be submitted 60 days after J
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 fem of an hour-by-hour If sting on magnetic tape of wind speed, wind direc-1 tion and atmospheric stability, and precipitation (if measured), or in the form l
l of joint frequency distributions of wind speed, wind direction, and atmospheric stability.** This same report shall include an assessment of the radiation doses i
i i
due to the radioactive liquid and gaseous effluents released from the unit or l
i station during the previous calendar year.
This same report shall also include j
en assessment of the radiation doses from radioactive liquid and gaseous effluents "One map shall cover stations near the SITE BOUNDARY; a second shall include 1
the more distant stations.
- In lieu of submission with the first half year Seelannual Radioactive Effluent i
Release Report, the licensee has the oi: tion of retaining this summary.cf required meteorological data on site in a file that shall be provided to the NRC upon request.
t i
t RIVER SEND - UNIT 1 6-18
.