ML20247L453
| ML20247L453 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/24/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247L458 | List: |
| References | |
| GL-88-06, GL-88-6, NUDOCS 8908010252 | |
| Download: ML20247L453 (34) | |
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' UNITED STATES
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. NUCLEAR REGULATORY. COMMISSION :
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' SOUTH CAROLINA ELECTRIC &' GAS COMPANY :
SOUTH CAROLINA PUBLIC SERVICE' AUTHORITY DOCKET NO. 50-395-VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE 4
Amendment No. 79 License No. NPF-12 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
- The applications for amendment by South Carolina Electric & Gas l
Company (the licensee), dated July 6,1987, as' supplemented May 16, l
July 18, and Decenber 22, 1988; dated January 6,1988; and dated l
March 31, 1987, as supplemented Decenber 21, 1987 and January L
31, 1989 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules
-and regulations set forth in'10 CFR Chapter I; I
B.
The facility will operate in conformity with the application,.
the provisions of the Act, and the rules and-regulations of the Comission; 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraphs 2..'.(2) and 2.C.(18) of Facility Operating License No. NPF-12 are hereby anended to read as follows:
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.2 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through' Amendment No. 79
, and'the Environmental Protection Plan contained in Appendix B,' are hereby incorporated in the license.
South Carolina' Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(IB) Fire Protection System (Section 9.5.1, SSER 4)
Virgil C. Summer Nuclear' Station shall implement and maintain in effect.all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility, and as approved in the SER (Safety Evaluation Report) dated February 1981- (and Supplements dated Jhnuary 1982 and August 1982) and Safety Evaluations dated May 22, 1986, November 26, 1986, and July 17, 1987 subject to the following provisions:
The licensee may make changes to the approved fire protection, program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of fire.
3.
This amendment is effective as of its date of issuance, and shall be implemented within 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:
Elinor G.-Adensam, Director Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
- SEE PREVIOUS CONCURRENCE (0GC concurrence was by C. Barth on 2/13/89 on Fire Protection sections and C. Woodhead on 4/4/89 on Organization Charts and administrative change sections) o n
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DATE:0f/d8/,89
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- 04/04/89
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ATTACHMENT TO LICENSE AMENDMENT fiO. 79 TO FACILITY OPERATING LICENSE NO. NPF-12 p0CKETNO.50-395 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised peges are identified by amendment number and contain vertical lines indicating the areas of change. Corresponding overleaf pages are also provided to maintain document completeness.
Remove Pages Insert Pages III III(overleaf)
IV IV VIII VIII XIV XIV 3/4 3-61 3/4 3-61 3/4 3-62 through 3/4 3-66d 3/4 7-26 3/4 7-25 3/4 7-26 through 3/4 7-36 83/4 3-3 B3/4 3-3 (overleaf)
B3/4 3-4 B3/4 3-4 B3/4 7-6 B3/4 7-6 B3/4 7-7 6-1 6 6-la 6-la 6-2 6-2 6-3 6-3 6-4 6-4 6-5 6A 6-6 6-6 l
6-7 6-7 6-8 6-8 6-9 6-9 6-10 6-10 6-11 6-11 6-12 6-12 6-13 6-13 6-14 6-14 6-14a 6-15 6-15 6-16 6-16 6-17 6-17 6-18 6-18 l
6-18a l
6-19 6-19 5-20 6-20 6-21 6-21 6-22 6-23
, c.
INDEX
- LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY...............................................
3/4 0-1 l
'3/4.1 REACTIVITY CONTROL' SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - Modes 1 and 2..........................
3/4 1-1 Shutdown Margin.- Modes 3, 4 and 5.......................
3/? 1-3 Moderator Temperature Coefficient........................
3/4 1-4 Minimum Temperature for Criticality......................
3/4 1-6 3/4.1.2 BORATION SYSTEMS Flow Path - Shutdown.....................................
3/4 1-7 Flow Paths - Operating...................................
3/4 1-8 Charging Pump - Shutdown.................................
3/4 1-9 Charging Pumps - Operating...............................
3/4 1-10 Borated Water Source - Shutdown..........................
3/4 1-11 Borated Water Sources - Operating........................
3/4 1-12 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height.............................................
3/4 1-14 Position Indication Systems - Operating..................
3/4 1-17 Position Indication System - Shutdown....................
3/4 1-18 Rod Drop Time............................................
3/4 1-19 Shutdown Rod Insertion Limit.............................
3/4 1+20 Control Rod Insertion Limits.............................
3/4 1-21 SUMMER-UNIT 1 III Amendment No. 79
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~',, l INDEX y,,
.LI'MITING' CONDITIONS FOR OPERATION AND SURVEIL' LANCE REQUIREMENTS g
I'.;
SECTION' PAGE 3/4'. 2 POWER DISTRIBUTION LIMITS.
K 3/4.2.1 AXI A L F LUX DI F F E R ENC E.....................................
3/4 2-1 V
- 3/4.2.2 HEAT FLUX 40T CHANNEL FACT 0R.............................
3/4 2-4'
'3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R.........................................
3/4 2-8 l
3/4.2.4 QUADRANT POWER TILT RATI0................................
3/4 2-12 i-..
3/4.2.5 DNB' PARAMETERS...........................................
3/4'2-15 3/4.3 INSTRUMENTATION:
'3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION......................
3/4 3-1
.3/4.3.24. ENGINEERED' SAFETY FEATURE-ACTUATION SYSTEM
-INSTRUMENTATION........................................
3/4 3-15~
3/4.3.'3 ~ MONITORING. INSTRUMENTATION Radi ati on Moni to ri ng.....................................
3/4 3-41 Movable Incore Detectors.................................
3/4 3-46 Seismic Instrumentation...................................
3/4.3-47
. Meteorological Instrumentation...........................
3/4 3-50 Remote Shutdown Instrumentation..........................
3/4 3-53 Accident Monitoring Instrumentation......................
3/4 3-56 Radioactive Liquid Effluent Monitoring Instrumentation.........................................
3/4 3-67 Radioactive Gaseous Effluent Monitoring Instrumentation........................................
3/4 3-73 Loose-Part Detection Instrumentation.....................
3/4 3-80 l
SUMMER - UNIT 1 IV Amendment No. 79
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE
, Safety Va1ves.............................................
3/4 7-1 Emergency Feedwater System...............................
3/4 7-4 Condensate Storage Tank...........
3/4 7-6 Activity.............................
3/4 7-7 Main Steam Line Isolation Va1ves.........................
3/4 7-9 Feedwater Isolation Va1ves...............................
3/4 7-9a 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........
3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................
3/4 7-11 3/4.7.4 SERVICE WATER SY5 TEM.....................................
3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK......................................
3/4 7-13 3/4.7.6 CONTROL ROOM NORMAL AND EMERGENCY AIR HANDLING SYSTEM....
3/4 7-14 3/4.7.7 SNUBBERS.................................................
3/4 7-16 3/4.7.8 SEALED SOURCE CONTAMINATION..............................
3/4 7-23 3/4.7.9 AREA TEMPERATURE MONITORING..............................
3/4 7-37 I
SUMMER - UNIT 1 VIII Amendment No. 7), 79
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INDEX u;
Q,
-q fBASES SECTION PAGE m
3/4.7 PLANT SYSTEMS x
L.
- 3/4.7.1'. ' TURBINE' CYCLE...........................................
.B 3/4 7.1I 3/4.7.2. STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.....-....
B 3/4 7-3 l-
.f3/4'7.3-COMPONENT COOLING WATER SYSTEM........................
B'3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM.....................................
B 3/4 7-3
- 3/4.7.5 ULTIMATE' HEAT SINK.....................................'.
B 3/4 7 :3/4.7.6.. CONTROL ROOM NORMAL AND.
EMERGENCY AIR HANDLING SYSTEM..........................
B 3/4 7-4 1
,3/4.7.71 SNUBBERS................................................
B 3/4'7-4
'3/4.7.8 SEALED SOURCE CONTAMINATION............................
B 3/4 7-6 3/4.7'9 AREA TEMPERATURE M0NITORING.............................
B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS.
-3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES AND
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ONSITE POWER DISTRIBUTION SYSTEMS..........
B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTION DEVICES.................
B 3/4 8-3' i
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SUMMER - UNIT 1 XIV Amendment No. $$. $1, 79
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1 THIS PAGE INTENTIONALLY LEFT BLANK Pages 3/4 7-26 through 3/4 7-36 have been deleted.
SUMMER - UNIT 1 3/4 7-25 Amendment No. 79
4 THIS PAGE INTENTIONALLY LEFT BLANK Pages 3/4 3-62 through 3/4 3-66d have been deleted.
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l SUMMER - UNIT 1 3/4 3-61 Amendment No. 79
.,8 INSTRUMENTATION BASES REACTOR PROTECTION SYSTEM AND ENGINEERED SAFETY FEATURE ACTUATION SYSTEM
- INSTRUMENTATION (Continued)
The Engineered Safety Feature Actuation System interlocks perform the following functions:
P-4 Reactor tripped - Actuates turbine trip, closes main feedwater valves on T,yg below setpoint, prevents the opening of the main feedwater valves which were closed by a safety injection or high steam generator water level signal, allows safety injection block so that components can be reset or tripped.
Reactor not tripped prevents manual block of safety injection.
P-11 On increasing pressurizer pressure, P-11 automatically reinstates safety injection actuation on low pressurizer pressure.
On' decreasing pressure, P-11 allows the manual block of safety injection actuation on low pressurizer pressure.
P-12 On increasing primary coolant loop temperature, P-12 automatically reinstates safety injection actuation and steam line isolation on low steam line pressure, and removes a blocking signal from the steam dump system. On decreasing primary coolant loop temperature, P-12 allows the manual block of safety injection actuation and steam line isolation on low steam line pressure and automatically provides a blocking signal to the steam dump system.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum l
complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.
N For the purpose of measuring F a full incore flux map is used.
Quarter-core flux maps, as defined kn(Z) or FWCAP-8N8, June 1976,maybeusedin recalibration of the excore neutron flux detection system, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.
SUMMER - UNIT 1 B 3/4 3-3
L. (.
e' INSTRUMENTATION-
- BASES i
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-3/4.3.3.3 SEISMIC INSTRUMENTATION g
The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
This capability is required to permit comparison of the measured response to that.used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100.
The instrumentation is consistent l -
with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earth-quakes," April 1974.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY Of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses'to the public as a result of routine or accidental release of radioactive materials to.the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that
-sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG 0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."
SUMMER - UNIT 1 8 3/4 3-4 Amendment No. 79 I
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P'LANT SYSTEMS BASES-3/4.7.8: SEALED SOURCE CONTAMINATION.
The limitations on removable contamination for sources requiring. leak.
testing,' including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
This limitation will ensure that-leakage from. byproduct, source, and'special nuclear material sources will not exceed allowable intake values.
Sealed-sources are. classified into three groups according to their use, with-surveillance requirements commensurate with the probability of damage to a source in that group.~
Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism (i.e. sealed sources within radiation monitoring or boron measuring devices) are considered to' be stored and.need not be. tested.unless they are rer.oved from the shielded mechanism.
. 3/4.7.9 AREA TEMPERATURE MONITORING-The area temperature limitations ensure that safety-related equipment will not be' subjected to temperatures in excess of their environmental quali-:
fication temperatures.
Exposure to excessive temperatures may degrade equipment and can cause a' loss of its OPERABILITY.
The temperature limits include an allowance for ~ instrument error of 2 F.
SUMMER - UNIT 1 B 3/4 7-6 Amendment No. 79
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6.'0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY-6.1.1 The General Manager, Nuclear Plant Operations 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 shall be responsible for unit operations.
A management directive to this effect, signed by the Vice President, Nuclear Operations, shall be reissued to all station personnel on an annual basis.
- 6. 2 ORGANIZATION
. 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Offsite and Onsite organizations shall be established for unit operation-and corporate management, respectively.
The offsite and onsite organiza-tions 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 from the highest levels through intermediate levels to and including all operating organization positions.
Those relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
The organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).
b.
The General Manager, Nuclear Plant Operations, shall be responsible for overall unit safe operation and shall have control over onsite activities necessary for safe operation and maintenance of the plant.
c.
The Vice President, Nuclear Operations, shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
The individuals who train the operating staff and those who carry out the 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 6.2-1.
i SUMMER - UNIT 1 6-1 Amendment No. 78, 79
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b.
At least one licensed Reactor Operator shall be-in the. control room when fuel is in the reactor.
In addition, while the unit is in MODE 1, 2, 3 or 4, at least one Licensed Senior Reactor Operator shall be=in the Control Room.
A health physics technician # shall be on' site when fuel is in the c.
reactor.
d.
All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or. Senior Reactor _ Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
Administrative procedures shall be developed and implemented to e.
limit the working hours of unit staff who perform safety-related functions; e.g., senior reactor' operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.
Adequate shift coverage shall be maintained without routine heavy use of overtime.
However, in the event that unforeseen problems require substantial amounts of overtime to be used, er during extended '
periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:
a.
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.
b.
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.
c.
A break of at least eight hours should be allowed between work periods, including shift turnover time.
d.
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 General Manager, Nuclear Plant Operations, or his deputy, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Except during extended shutdown periods, controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the General Manager, Nuclear Plant Operations, or his designee to j
assure that excessive hours have not been assigned.
Routine devia-
{
tion from the above guidelines is not authorized.
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- The health physics technician composition may be less than the minimum require-ments 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.
SUMMER - UNIT 1 6-la Amendment No. 18,57,79 1
i b, TABLE'6.2-1
. MINIMUM SHIFT CREW COMPOSITION SUMMER UNIT 1 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL' POSITION' MODES 1, 2,'3, &.4 MODES 5 & 6 SS 1
1-CRF.
1 None
'R0 2
l' A0 2
1 STA 1
None SS - Shift Supervisor with a Senior Reactor l0perators License on Unit CRF - Control Room Supervisor with a Senior Reactor Operators' License on Unit 1 R0 - Individual with a Reactor Operators License on Unit 1 AD. - Auxiliary Operator STA - Shift Technical Advisor Except for the Shift Supervisor, the Shift Crew Composition may.be one less
.than the minimum. requirements of Table 6.2-1 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 accommodate unexpected absence of on-duty shift crew members provided'immediate action is taken to restore the Shift Crew Composition.to within the minimum requirements of Table 5.2-1.
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 Control Room Supervisor from the Control Room while the unit is in MODE 1, 2, 3 or 4, an individual.(other than the Shift Technical Advisor) with a valid SRO 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 MODE 5 or 6, an individual with'a valid R0 or'SR0 license shall be designated to assume the Control Room command function.
, SUMMER - UNIT 1 6-2 Amendment No. 78,55,79 l
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ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)-
FUNCTION 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances _, industry advisories, Licensee Event Reports and other sources
'of plant design and operating experience information, including plants of-similar design, which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The ISEG shall be composed of a multi-disciplined dedicated onsite group with a minimum assigned complement of five engineers or appropriate specialists.
RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant
-activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for procedure revisions, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to the General Manager, Nuclear Safety.
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6.2.4 SHIFT TECHNICAL ADVISOR i
The Shift Technical Advisor shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.
- 6. 3 UNF STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable positions and the supplemental require-ments specified in Sections A and C of Enclosure 1 of the March 28, 1980 letter to all licensees as clarified in NUREG-0737,Section I. A.2.1, except for the Associate Manager, Health Physics who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, the Shift Technical Advisor who shall meet or exceed the qualifications referred to in Section 2.2.1.b of Enclosure I cf the October 30, 1979 NRC letter to all operating nuclear power plants, and the members of the Independent Safety Engineering Group, each of whom shall have a Bachelor of Science degree or registered Professional Engineer and at least two years experience in their field.
At least one year experience shall be in the nuclear field.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained and shall meet or exceed the requirements and recommendations of Sections 5.2 and 5.5 of ANSI 3.1-1981 and 10 CFR 55.59, as committed to in l
Appendix 3A of the Final Safety Analysis Report.
- Not responsible for sign-off function.
SUMMER - UNIT 1 6-3 Amendment No.75,55,79
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'6.5' REVIEW AND AUDIT 6.5.1 PLANT SAFETY REVIEW COMMITTEE (PSRC)
FUNCTION 6.5.1.1 The PSRC shall function to advise the General Manager, Nuclear' Plant?
Operations on all matters related to. nuclear safety.
' COMPOSITION
- 6. 5.1. 2 The Plant Safety Review Committee shall be composed ~of the:
Chairman:
General Manager, Nuclear. Plant Operations or General Manager, Operations and Maintenance Member:
Manager, Operations Member:
General Manager, Station Support Member:
Manager, Maintenance Services Member:
Manager, Core Engineering and Nuclear Computer Services Member:
Manager, Chemistry and Health Physics Member:
Manager, Design Engineering ALTERNATES 6.5.1.3 'All alternate members shall be appointed in writing by the PSRC Chairman to serve on a temporary basis; however, no more than two alternates including the Chairman's alternate, if applicable, shall' participate as voting members in PSRC activities at any one time.
MEETING FREQUENCY 6.5.1.4 The PSRC shall meet at least once per calendar month and as convened by the PSRC Chairman or his designated alternate.
QUORUM
- 6. 5.1. 5 The minimum quorum of the PSRC necessary for the performance of the PSRC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and three members including alternates.
RESPONSIBILITIES 6.5.1.6 The Plant Safety Review Committee shall review:
a.
Station administrative procedures and changes thereto, b.
The safety evaluations for 1) procedures, 2) changes te procedures, equipment or systems, and 3) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question and all programs required by Specification 6.8 and changes thereto.
l c.
Proposed procedures and changes to procedures, equipment or systems which may involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
SUMMER - UNIT 1 6-4 Amendment No. JE, 79
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. Proposed tests or experiments'which may involve an unreviewed safety question as. defined in Section 50.59, 10 CFR.
Proposed. changes to. Technical Specifications or the Operating License, e.
f.
Reports of violations.of codes, regulations, orders, Technical' Specifications, or Operating License requirements having nuclear safety significance or reports of abnormal degradation of systems designed to contain radioactive material.
g.
Reports of significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
h.
Review of all REPORTABLE EVENTS, i.
All recognized indications of an unanticipated deficiency in some aspect' of design or operation of safety related structures, systems, or components.
j.
The plant Security Plan and changes thereto.-
k.
The Emergency Plan and changes thereto.
L Items which may constitute a potential nuclear safety hazard as identified during' review of facility operutions.
Investigations or analyses of special subjects as requested by the m.
Chairman of the Nuclear Safety Review. Committee.
n.
The unexpected offsite1 release of radioactive material and the report as described in 10 CFR 50.73.
o.
Changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION
- MANUAL, p.
.The plant Fire Protection Program and revisions there to.
l AUTHORITV 6.5.1.7 The Plant Safety Review Committee shall:
a.
Recommend in writing to the General Manager, Nuclear Plant l
Operations, approval or disapproval of items considered'under
- 6. 5.1. 6a, c, d, e, j, and k above.
b.
Render determinations in writing to the General Manager, Nuclear Plant l Operations, with regard to whether or not each item considered under 6.5.1.Ga, c, and d above constitutes an unreviewed safety question.
c.
Make recommendations in writing to the General Manager, Nuclear Plant l
Operations, that actions reviewed under 6.5.1.6(b) above did not con-stitute an unreviewed safety question.
3 d.
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, Nuclear Operations and the Nuclear Safety Review Committee of dis-agreement between the PSRC and the General Manager, Nuclear Plant Operations however, the General Manager, Nuclear Plant Operations shall have respor.sibility for resolution of such disagreements pursuant to 6.1.1 above.
SUMMER - UNIT 1 6-5 Amendment No. 75, 79
ADMD11STRATIVE CONTROLS RECORDS 6.5.1.8 The Plant Safety Review Committee shall maintain written minutes cf each PSRC meeting that, at a minimum, document.the results of all PSRC activ-ities performed under the responsibility and authority provisions of these technical specifications.
Copies shall be provided to the Vice President Nuclear Operations and the Chairman of the N eher Safety Review Committee.
- 6. 5.' 2 NUCLEAR SAFETY REVIEW COMMITTEE (NSRC)
L FUNCTION 6.5.2.1 The Nuclear Safety Review Committee shall function to provide independent ' review and audit of designated activities in the areas of:
a.
nuclear power plant operations b.
nuclear engineering I'
c.
chemistry and. radiochemistry d.
metallurgy e.
instrumentation and control f.
radiological safety g.
mechanical and electrical engineering h.
quality assurance practices COMPOSITION-6.5.2.2 NSRC shall consist of a Chairman and four or more other members appointed by the Executive Vice President, Operations, in consultation with the Vice President, Nuclear Operations.
No more than a minority of the members of the NSRC shall have line responsibility for the operation of the unit.
The NSRC members shall hold a Bachelor's degree in an engineering or physical science field & equivalent experience and a minimum of five years of technical experience of which a minimum of three years shall be in one or more of the disciplines of 6.5.2.la through h.
In the aggregate, the membership of the committee shall provide specific practical experience in the majority of the disciplines of 6.5.2.la through h.
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the Executive Vice President, Operations, in consultation with the Vice President, Nuclear l
Operations; however, no more than two alternates shall participate as voting l
members in NSRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSRC Chairman to provide expert advica to the NSRC.
SUMMER - UNIT 1 6-6 Amendment No. 78. 79 l
e ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.2.5 The NSRC shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once pe' six months thereafter.
QUORUM 6.5.2.6 A quorum of the NSRC necessary for the performance of the NSRC review and. audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least 3 NSRC members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
REVIEW 6.5.2.7 The NSRC shall review:
The safety evaluations for 1) changes to procedures, equipment or a.
systems, and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, 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 Section 50.59, 10 CFR.
Proposed tests or experiments which involve an unreviewed safety c.
question as defined in Section 50.59, 10 CFR.
d.
Proposed changes to Technical Specifications or this Operating License.
Violations of codes, regulations, orders, Technical Specifications, e.
license requirements, or 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 REPCRTABLE EVENTS.
h.
All recognized indications of an unanticipated deficiency in some aspe:t of design or operation of structures, systems, or components that could affect nuclear safety, i.
Reports and meetings minutes of the Plant Safety Review Committee.
SUMMER - UNIT 1 6-7 Amendment No. 35, 79 l
_ _ _ _ _ _ _ = _ - _
J *[ 34 ADMINISTRATIVE CONTROLS AUDITS-6.5.2.8.The NSRC shall have cognizance of'the audits listed below.' Audits may be performed by using established SCE&G groups such as the ISEG and QA or by-o outside groups as determined by the NSRC.
Audit reports or summaries will be
- the basis.for NSRC action:
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 performance, training and qualifications of the entire unit staff at 1 east once per 12 months.
The results of actions taken to correct deficiencies occurring in c.
unit equipmer.t. 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.50, at least once per 24 months.
The Emergency Plan and implementing procedures at least once per e.
12 months.
f.
The Security Plan and implementing procedures at least once per 12 months.
g.
Any other area of unit operation considered appropriate by the NSRC, Executive Vice President, Operations, or the Vice President, Nuclear Operations.
h.
The Fire Protection Program and implementing procedures at least once per 24 months.
i.
An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or a qualified outside firm.
j.
An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
k.
The radiological environmental monitoring program and the results thereof, including the performance of activities required by the quality assurance program per R.G. 4.15 Rev.1, February 1979, at least once per 12 months.
1.
The 0FFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
m.
The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes at least once per 24 months.
AUTHORITY 6.5.2.9 The NSRC shall report to and advise the Executive Vice President, Operations on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
SUMMER - UNIT 1 6-8 Amendment No.),/7,79 l
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ADMINISTPsATIVE CONTROLS
. RECORDS 6.5.2.10. Records of NSRC activities shall be prepared, approved and distributed as indicated below:
Minutes of.each NSRC meeting shall'be prepared, approved and forwarded a.
to the Executive Vice President, Operations, and the Vice President, l
Nuclear Operations within 14 days following each meeting.
1 b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be pre-pared, approved and forwarded to.the Executive Vice President, Opera-tions, and.the Vice President, Nuclear Operations.within 14 days following completion of the review, Audit summary reports encompassed by Section 6.5.2.8 above, shall be c.
forwarded to the NSRC, the Executive Vice President, Operations, and the Vice President, Nuc 4ar Operations.
Full audits.shall be forwarded to the management positions responsibir'for the areas audited within 30 days after completion of the audit by the auditing organization.
6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:
Procedures required by Technical Specification 6.8 and other proce-a.
dures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approvedi Each such procedure or procedure change shall be reviewed by an individual / group other than the individual / group which prepared the procedure or procedure change, but who may be from the same organization as the individual / group which prepared the procedure or procedure change.
Procedures other than Administrative Procedures will be approved as delineated in writing by the General Manager, Nuclear Plant Operations.
The General Manager, l
Nuclear Plant Operations will approve administrative procedures, security implementing procedures and emergency plan implementing procedures.
Temporary approval to procedures which clearly do not change the intent of the approved procedures can be made by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License.
For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to approve the proceduro shall approve the change.
b.
Proposed changes or modifications to plant nuclear safety-related structures, systems and components shall be reviewed as designated by i
the General Manager, Nuclear Plant Operations.
Each such modifica-I tion shall be designed as authorized by Engineering Services and shall be reviewed by an individual / group other than the individual /
group which designed the modification, but who may be from the same organization as the individual / group which designed the modifications, i
Implementation of modifications to plant nuclear safety-related structures, systems and components shall be concurred in by the General Manager, Nuclear Plant Operations.
g SUMM E - UNIT 1 6-9 Amendment No. M, 79
M'.
ADMINISTRATIVE CONTROLS Proposed tests and experiments which affect plant nuclear safety and c.
are not addressed in the Final Safety Analysis Report shall be a
reviewed by an indiv. dual / group other~than the individual / group-which prepared the proposed test or experiment.
d.
Events reportable pursuant to the Technical Specification 6.9'and
. violations of Technical Specifications shall be investigated and a report prepared which evaluates the event and which provides recom-mendations to prevent recurrence.
Such report shall be approved -by-o the General Manager, Nuclear Plant Operations and forwarded to the Chairman of the Nuclear Safety Review Committee, Individuals responsible for reviews performed in.accordance with e.
- 6. 5. 3.1. a, 6. 0. 3.1. b, 6. 5. 3. L c and 6. 5. 3.1. d shall be members of the plant staff that meet or exceed the qualification requirements o_f Sec-
' tion 4 of ANSI 18.1, 1971, as previously designated by the General Manager, Nuclear Plant Operations.
Each such review shall include a determination of whether or not additional,-cross-disciplinary, review is necessary.
If deemed nece?sary, such review shall be performed by the review personnel of the appropriate discipline.
f.
Each review will include a determination of whether or not an unreviewed safety question is involved.
RECORDS 6.5.3.2 Records of the above activities shall be provided to the General Manager, Nuclear Plant Operations, PSRC and/or NSRC as necessary for required reviews.
6.6 REPORTABLE EVENT ACTION j
6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
The Commission shall be notified and/or a report submitted pursuant a.
to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the PSRC and the results of this review shall be submitted to the NSRC and the Vice President, Nuclear Operations.
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 one hour.
The Vice President, Nuclear Operations and the NSRC 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 Lirrit Violation Report shall be prepared.
The report shall be reviewea ay the PSRC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
c.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRC and the Vice President, Nuclear Operations within 14 days of i
the violation.
t.
SUMMER - UNIT 1 6-10 Amendment No. 78,N,79
~
c ADMINISTRATIVE CONTROLS l
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 maintained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of Regulatory a.
Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
c.
Surveillance and test activities of safety-related equipment.
d.
Security Plan.
e.
f.
g.
OFFSITE DOSE CALCULATION MANUAL.
1.
Effluent and environmental monitoring program using the guidance in Regulatory Guide 4.15, Revision 1, February 1979.
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed prior to implementation as set forth in 6.5 above.
6.8.4 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
The systems include the chemical and volume control, letdown, safety injection, residual heat removal, nuclear sampling, liquid radwaste handling, gas radwaste handling and reactor building spray system.
The program shall include the following:
(i) Preventive maintenance and periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.
b.
In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.
This program shall include the following:
(i) Training of personnel, (ii) Procedures for monitoring, and j
(iii) Provisions for maintenance of sampling and analysis equipment.
I i
a SUMMER - UNIT 1 6-11 Amendment No.75,6,//7 l
79 l
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~
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p i
'~
ADMINISTRATIVE CONTROLS ~
. c.
Secondary Water Chemistry
'A program for~ monitoring of secondary water chemistry to inhibit steam-generator tube degradation.
This program shall include:
(i) Identification of. a sampling ' schedule for the critical variables and control points for these variables, (ii) Identification.of.the procedures used to measure,the values.of the critical variables',
(iii) Identification'of process sampling points, including monitoring the. discharge of the condensate pumps for evidence of condenser in-leakage.
(iv) Procedures for the recording and management of data, (v) Procedures defining corrective actions for all off-control point chemi A ry conditions, (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence-and timing of administrative events required to initiate corrective action.
d.
Postaccident 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:
(i) Training personnel, n
(ii) Procedures.for sampling and analysis, (iii) Provisions for maintenance of sampling and analysis equipment.
SUMMER - UNIT 1 6-12 Amendment No.35.5/,79
c
'r ADMINISTRATIVE CONTROLS 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 Regional Administrator Office of Inspection and Enforcement 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 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 the nuclear, thermal, or hydraulic performance of the plant.
- 6. 9.1. 2 The startup report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test 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 completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every three months until all three events have been completed.
ANNUAL REPORT 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, and other personnel (including contractors) receiving exposures greater than 100 mr manremexposureaccordingtoworkandjobfunctions,g/yrandtheirassociated l
e.g., reactor operations j
and surveillance, inservice inspection, routine m intenance, special maintenance
{
(describe maintenance), waste processing, and refu3 ling.
The dose assignments
)
i l
to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.
In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
MThis tabulation supplements the requirements of S20.407 of 10 CFR Part 20.
j SUMMER - UNIT 1 6-13 Amendment No. 79
S.
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ADMINISTRATIVE CONTROLS This report shall also include the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8.
The following information shall be included:
(1) Reactor power history starting
- hours prior to the first sample in which the limit was exceeded; (2) Results of. the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radiciodine concentrations; (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 concentration 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.
ANNUAL RADIOLOGICAL ENVIRONMENTAL, OPERATING REPORT 6.9.1.6 Routine radiological environmental operating reports covering the oper1 tion 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.
6.9.1.7 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 comparison with preoperational studies, operational controls (as appropriate), 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 Specifica-tion 3.12.2.
If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following:
a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3.
I SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 dayc ef ter January 1 and July 1 of each year.
The period of the first report shall begin with the date of initial criticality.
SUMMER - UNIT 1 6-14 Amendment No.79
4 ADMINISTRATIVE CONTROLS 6.9.1.9 The radioactive effluent release reports shall include a-summary of the quantities of-radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases Of Radio-active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
The radioactive' effluent release report to be submitted within 60 days.after
. January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year.
This. annual summary may be either.in the. form of.'an hour-by-hour listing of wind speed, wind direction, and atmo-spheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and.
atmospheric stability.
This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.
This same report shall also include'an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities -
'inside the site boundary (Figures 5.1-3 and 5.1-4) during the report. All assumptions used.in-making these assessments (i.e., specific activity, exposure time-and location) shall be included in these reports.
Historical annual average meteorology or meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses.
The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (0DCM).
The radioactive effluent release report to be submitted within 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 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.
Acceptable methods for calculating the dose contribu-tion.from liquid and gaseous effluents are given in Regulatory Guide 1.109, i
Rev. 1.
The radioac'.ive effluents release shall include the following information for eaca type of solid waste shipped offsite during the report period:
a.
Container volume, o.
Total curie quantity (specify whether determined by. measurement or estimate),
c.
Principal radionuclides (specify whether determined by measurement or estimate),
d.
Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),
SUMMER - LNIT 1 6-15 Amendment No. H, 79 l
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1 ADMINISTRATIVE CONTROLS' Type of container ~(e.g.,'LSA, Type A, Type B, Large Quantity), and e.
f.
Solidification agent (e.g., cement, urea formaldehyde).
The rad'oactive effle.nt release reports shall include unplanned releases from site _ to. Unrestricted areas of. radioactive materials in gaseous and liquid effluents on a quarterly basis.
-Tne radioactive effluent release reports shall include any changes to the Process Control Program (PCP) made during the reporting period.
< MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, in-cluding documentation of all ~ challenges to the PORV's or safety 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 Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective.
In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted as set forth in 6.5 above.
RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.11 The AFD limits, the W(z) Functions for RA0C and Base Load operation and the value for APLND (as required) shall be established for each reload core and implemented prior to use.
The methodology used to generate the W(z) functions for RAOC and Base Load 1
ND Operation and tha value for APL shall be those previously reviewed and approved by the NRC.*
If changes to these methods are deemed necessary they will be evaluated in accordance with 10 CFR 50.59 and submitted to the NRC for review and approval prior to their use if the change is determined to involve an unreviewed safety question or if such a change would require amendment of previously submitted documentation.
A report containing the AFD limits, the W(z) functions for.RAOC and Base Load operation and the value for APLND (as required) shall 6 provided to the NRC document control desk with copies to the regional adm_ 4trator end the resident inspector within 30 days of their implementation.
ND Any'informationneededtosupportW(z),W(z)$Land APL will be by request from the NRC and need not be included in thi report.
- WCAP-10216 P-A " Relaxation of Constant Axial Offset Control-F Surveillance Technical Specification."
q SUMMER - UNIT 1 6-16 Amendment No. 79 i
, t ;r ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Office of Inspection and Enforcement Regional Office within the time period.
specified for each report.
6 10 RECORD RETENTION 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.
6.10.1 The following records shall be retained for at least five. years:
a.
Records and logs of unit operation covering time interval at each.
power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety, c.
All REPORTABLE EVENTS submitted to the Commission.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
Records of changes made to the procedures required by e.
Specification 6.8.1.
f.
Records of radioactive shipments.
g.
Records of sealed source and fission detector laak tests and results.
h.
Records of annual physical inventory of.all sealed source material' of record.
6.10.2 The following records shall be retained for the duration of the Unit Operating License.
a.
Records and drawing changes reflecting unit design modifications made 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.
c.
Records of radiation exposure for all individuals entering radiation control areas.
d.
Records of gaseous and liquid radioactive material released to the environs.
SUMMER - UNIT 1 6-17 Amendment No. 79
Le a
(
o
- . m...
l '
ADMINISTRATIVE CONTROLS.
e..
Records of transient or operational cycles'for those unit components
? identified in. Table 5.7-1.
' f.
- Records of reactor. tests and experiments.
g.
Records of training and qualification for current members of the unit staff.
h.
. Records of in-service inspections performed pursuant to these Technical Specifications.
i' Records of Quality Assurance activities as specified in the NRC's approved SCE&G position on Regulatory Guide 1.88, Rev. 2, October-1976.
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 PSRC and the NSRC.
1.
Records of-the service lives of all hydraulic and mechanical snubbers defined'in Section 3.7.7 including the date~at which the service life commences and associated installation and maintenance records.
Records of secondary water sampling and water quality.
m.
n.
Records of analysis required by the radiological environmental monitoring program.'
6.11 RADIATION PROTECTION PROGRAM I
Procedures' for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA'
]
I 6.12.1 In lieu of the " control device" or " alarm signal" required by L
paragraph 20.203(c)(2) of 10 CFR 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 area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).* Any individual or groun of individuals permitted to enter such areas shall be provided with or accomi.. tied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
" Health Physics personnel or personnel escorted by Health Physics personnel l
shall be exempt from the RWP issuance requirement during the performance of j
their assigned radiation protection duties, provided they otherwise comply with approved radiation protection procedures for entry into high radiation areas.
1 i
SUMMER - UNIT 1 6-18 Amendment No. M,0.75 1
79 i
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. ADMINISTRATIVE' CONTROLS 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. level in the area has been established and personnel have been made bowledgeable of them.
A health physics qualified. individual (i.e., qualified in' radiation c.
protection procedures) with a radiation dose rate monitoring device.
who is responsible for providing positive control over the activities within the area and shall perform periodic radiation
. surveillance at the frequency specified by the facility Health-Physicist in the. Radiation Work Permit.
6.12.2 I'n addit' ion to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors.to
. prevent unauthorized entry, and the keys shall be maintained under the admin-istrative control of the Shift Foreman on duty and/or health physics supervision.
Doors shall remain locked except during periods of access by personnel under an-
-approved RWP which shall specify the dose rate levels in the immediate work area.
The maximum allowable stay time for individuals in that area shall be established prior to entry.
For individual areas accessible to personnel with radiation
' levels such that a major portion of the body could receive in one hour a dose in excess'of 1000 mrem ** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around tne individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.
In lieu of the stay time specification of the RWP direct or.
remote (such as use-of closed circuit TV cameras) continuous surveillance shall 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 semi-annual Radioactive Effluent Release Report for the period in which the change (s) was t
made.
This submittal shall contain:
a.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; b.
A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and
^^ Measurement made at 18" from source of radioactivity.
SUMMER - UNIT 1 6-19 Amendment No. M, 79 t_-_-
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' ADMINISTRATIVE CONTROLS c.
Documentat bn of the fact that the change has been reviewed'and found acceptable by.the PSRC.
2 Shallibecome effective upon review and acceptance as set forth in 6.'5 above.
l-
.6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6.14.1-The ODCM shall be approved by.the Commission prior to implementation.
6.14.2-Licensee initiated changes.to the ODCM:
1.
Shall be submitted to the Commission in the Monthly Operating Report within 90 days of the date the change (s) was made effective.
This submittal shall contain:
a.
Sufficiently detailed information to totally support the rationale.
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 c.
Documentation of the fact that the change has been reviewed and l
found acceptable by the PSRC.
~2.
Shall become effective upon review and acceptance as set forth.in 6.5 above.
6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and SoTid) 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid).
I'.
Shall be reported to the Commission in the Monthly Opercting Report for the period in which the evaluation was reviewed by the Plant Safety Review Committee.
The discussion of each change shall contain:
a.
A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; b.
Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c.
A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; d.
An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differs from those previously predicted in the license application and amendments thereto; SUMMER - UNIT 1 6-20 Amendment No. 6,79 i
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4 c c>
ADMINISTRATIVE CONTROLS An evaluation of the change which shows the expected maximum e.
exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto; f.
A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; g.
An estimate of the exposure to plant operating personnel as a result of the change; and h.
Documentation of the fact that the change was reviewed and found acceptable by the PSRC.
2.
Shall become effective upon review and acceptance as set forth in 6.5 above.
' SUMMER - UNIT 1 6-21 Amendment No. 35.79
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