ML20006E036
| ML20006E036 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 02/01/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006E035 | List: |
| References | |
| GL-88-06, GL-88-6, NUDOCS 9002160130 | |
| Download: ML20006E036 (18) | |
Text
- - - - -... -.... - -.........
'o UNITED STATES f!'
. NUCLEAR REGULATORY COMMISSION r
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WASHINGTON, D. C. 20555 o
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LONG. ISLAWD.LICRTING. COMPANY DOCKET kQ. 50 322-
.SWOREHAW.kUCLEAR. POWER. STATION AMENDMENT.10 FACILITY. 0&IRAIING. LICENSE -
Amendment No. 2 License No. NPF-82 1.
The Nuclear Regulatory Commission (the Commission) has found that A.
The application for amendment by Long Island Lighting Company (the licensee), dated June 13, 1988, complies with the standards and requirementsoftheAtomicEnergyActof1954,asamended(theAct),
'and the Comission's rules and regulations set forth in 10 CFR Chapter 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 coanon 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 paragraph 2.C.(2) of Facility Operating License No. NPF-82 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 2 are hereby incorporated into this license.
Long Island Lighting Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plen.
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION.
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:~ February 1,1990 1
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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v Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to=the Technical Specifications Date of Issuance:
February 1, 1990 j
i ATTACHMENT TO LICENSE AMENDMENT NO.
2 FACILITY OPERATING LICENSE N0. NPF-82 DOCKET NO. 50-322 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf pages provided to maintain document completeness.*
Remove Insert xix xix xx xx*
xxi xxi xxii xxi1*
6-1 6-1 6-2 6-2 6-3 6-3 6-4 6-4 6-5 6-5*
6-6 6-6 6-9 6-9 6-10 6-10*
6-11 6-11 6-12 6-12
o INDEX s
l ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY,.
6-1 6.2 ORGANIZATION..............................................
6-1 6.2.1 NUCLEAR ORGANIZATION.................................
6-1 6.2.2 UNIT STAFF...........................................
6-2 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP..................
6-6 FUNCTION..............................................
6-6 COMPOSITION..........................................
6-6 RESP 0NSIBILITIES.....................................
6-6 R E CO R 0 5..............................................
6 - 6 6.2.4 SHI FT TECHNICAL ADVI SOR..............................
6-6 6.' 3 UNIT STAFF QUALIFICATIONS...............................
6-6 6.4 TRAINING.,........,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
g_,
6.5 REVIEW AND AUDIT.........................................
6-7 6.5.1 REVIEW OF OPERATIONS COMMITTEE (R0C)................. 7 FUNCTION.............................................
6-7 COMPGSITION.........................................
6-7 ALTERNATE'...........................................
6-7 MEETING FREQUENCY....................................
6-7 QUORUM...............................................
6-7 RESPONSIBILITIES.....................................
6-8 RECORDS..............................................
6-9 15. 5. 2 NUCLEAR REVIEW BOARD (NRB)...........................
6-9 FUNCTION.............................................
6-9 COMPOSITION..........................................
6-9 ALTERNATES...........................................
6-9 CONSULTANTS..........................................
6-10 MEETING FREQUENCY....................................
6-10 QUORUM...............................................
6-10 SHOREHAM - UNIT 1 xix Amendment No. 2 r
-.(
INDEX ADMINISTRATIVE-CONTROLS SECTION PAGE NUCLEAR REVIEW BOARD (NRB) (Continued)
REVIEW...............................................
6-10 AUDITS.............................................
6-11 RECORDS...............
6-11 6.6 REPORTABLE EVENT ACTION..........
6-12
- 6. 7 SAFETY LIMIT VIOLATION....................................
1 6-12 6.8 PROCEDURES AND PROGRAMS......
6-13 6.9 REPORTING REQUIREMENTS...................................
6-14 6.9.1 ROUTINE REP 0RTS......................................
6-14 STARTUP REP 0RT.......................................
6-14 ANNUAL REP 0RTS.......................................
6-15 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT...
6-15 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT,......
6-16 HONTHLY OPERATING REPORTS...........................
6-18 6.9.2 SPECIAL REP 0RTS......................................
6-18 6.10' RECORD RETENTION.........................................
6-18 6.11 RADIATION PROTECTION PR0 GRAM.............................
6-19 6-12 HIGH RADIATION AREA......................................
6-20 6.13 PROCESS CONTROL PROGRAM (PCP)............................
6-21 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM)..
6-21 6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUIO, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS.
6-22 SHOREHAM - UNIT 1 xx
_ LIST OF FIGURES FIGURE PAGE
.3.1.5-1 SODIUM PENTABORATE SOLUTION TEMPERATURE /
CONCENTRATION REQUIREMENTS...................,,,,
3/4-1 21 3.1.5-2 SODIUM PENTABORATE SOLUTION CON
-TANK VOLUME......._,
. CENTRATION VS. NET 3/4 1-22 3.2.1-1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VS AVERAGE PLANAR EXPOS 3/4 2-2 3.2.1-2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VS. AVERAGE PLANAR EXPOSURE INITIAL CORE FUEL TYPE 8CR183....................
3/4 2-3 3.2.1-3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VS. AVERAGE PLANAR EXPOSURE INITI AL CORE FUEL TYPE 8CR711.....................
3/4 2-4 3.2.3-1 MINIMUM CRITICAL POWER RATIO (MCPR) VERSUS T AT RATED FLOW......
3/4 2-8 3 2.3-2 K FACTOR..........................,,,,,,,,,,,,,,
3,4 g.9 g
3.4.1.1-1 THERMAL POWER vs. CORE FLOW......................
3/4 4-3 3.4.6.1-1 MINIMUM REACTOR VESSEL METAL TEMPERATURE VS REACTOR VESSEL PRESSURE.......................
3/4 4-21 3.6.1.6-1 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURES.
3/4 6-10 3.6.2.1-1 DRYWELL PRESSURE VS. TIME INITIAL DRYWELL PRESSURE (17.72 psia).............,,,,,,,,,,,,,,,,,,,,,,,,,
3,4 g.3g 3.6.4-1 DRYWELL PRESSURE VS. TIME Ii41TIAL DRYWELL PRESSURE (15.72 psta)............................,,,,,,,,,
3,4 g.35 4.7.5-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST........
3/4 7-19 B 3/4 3-1 REACTOR VESSEL WATER LEVEL.......................
B 3/4 3-8 B 3/4.4.6-1 FAST NEUTRON FLUENCE (E>1MeV) AT 1/4 T AS A FUNCTION OF SERVICE LIFE........................
B 3/4 4-8 5.1.1-1 EXCLUSION AREA............
5-3 5.1.2-1 LOW POPULATION ZONE...............................
5-4 5.1.3-1 SITE B0UNDARY FOR RADI0 ACTIVE GASE0US AND LIQUID EFFLUENTS........................
5-5 6.2.1-1 CORPORATE-NUCLEAR ORGANIZATION (DELETED)..........
6-3 6.2.2-1 UNIT ORGANIZATION (DELETED)........................
6-4 SHOREHAM - UNIT 1 xxi Amendment No. 2
s
. s.
INDEX LIST OF TABLES TABLE PAGE 1.' 1 SURVEILLANCE FREQUENCY NOTATION..............'.....1-8
- 1. 2 OPERATIONAL CONDITIONS............................
1-9 2.2.1-1 REACTOR PROTECTION SYSTEM IN SETPOINTS..................STRUMENTATION 2-4 B2.1.2-1 UNCERTAINTIES USED IN THE DETERMINATION OF THE FUEL CLADDING SAFETY LIMIT....................
B 2 B2.1.2-2 NOMINAL VALUES OF PARAMETERS USED IN THE STATISTICAL ANALYSIS OF FUEL CLA
' SAFETY LIMIT...................DDING INTEGRITY B 2-4 3.3.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION.........
3/4 3-2 3.3.1-2 REACTOR PROTECTION SYSTEM RESPONSE TIMES..........
3/4 3-6 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS.........................
3/4 3-7 3.3.2-1 ISOLATION ACTUATION INSTRUMENTATION............... 3/4 3-11 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS.....
3/4 3-16 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME....
3/4 3-20 4.3.2.1-1 ISOLATION ACTUATION INSTRUMENTATION f
REQUIREMENTS...................... SURVEILLAN 3/4 3-23 3.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION...................................
3/4 3-28 i
3.3.3-2 EMERGENCY CORE COOLING SYSTEM ACTUATION l
INSTRUMENTATION SETPOINTS.........................
3/4 3-31 3.3.3-3 EMERGENCY CORE COOLING SYSTEM RESPONSE TIMES......
3/4 3-33 4.3.3.1-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS......... 3/4 3 3.3.4.1-1 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION...................................
3/4 3-37 3.3.4.1-2 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS.........................
3/4 3-38 SHOREHAM - UNIT 1 xxii
f.
(
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 Watch Engineer (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 Vice President-Nuclear Operations shall be reissued to all station personnel on an annual t
basis.
- 6. 2 ORGANIZATION NUCLEAR ORGANIZATION 6.2.1 An organization shall be established for unit operation'and corporate L
management.
This organization shall include the positions for activities af fecting the safety of the nuclear power plant, Lines of authority, responsibility and communication shall be a.
established and defined from the highest management levels through intermediate levels to and including all operating organizations positions.
These relationships shall be documented and updated, as appropriate, in the form 'of organizational 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 the SAR-and updated in accordance with 10 CFR 50.71(e).
b.
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, The Plant Manager shall be responsible for overall unit safe c.
operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant, 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.
UNIT STAFF 6.2.2 The station organization shall be subject to the following:
l
.Each on duty shift shall be composed of at least the minimum shift a.
crew composition shown in Table 6.2.2-1; SHOREHAM - UNIT 1 6-1 Amendment No. 2
.ADMfNISTRATIVE CONTROLS e
UNIT STAFF (Continued)-
i b.
- At least one licensed Reactor Operator shall be in the control room L
when fuel is in the reactor.
In addition, while the unit is in OPERATIONAL CONDITION 1, 2 or 3, 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 licensed Senior Reactor-Operator Limited to Fuel Handling who has no other concurrent.
responsibilities during this operation; A site fire brigade of at least five members shall be maintained-on-e.
i site at all times *,
The fire brigade shall not include the Watch Engineer, the Shif t Technical. Advisor, nor the two other members L
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 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 Reactor Operators, licensed Reactor Operators, health physicists, auxiliary operators, and key maintenance personnel).
Adequate shift coverage shall be maintained without routine heavy, use of overtime.
The objective shall be-to have operating personnel work a normal 8-hour day, 40-hour. week while the unit is operating.
However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shut-down for refueling, major maintenance, or major unit modification, on a temporary basis the following guidelines shall be followed:
1.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
2.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.
3.
A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time.
=-
- The Health Physics 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.
SHOREHAM - UNIT 1 6-2 Amendment No. 2 i
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U.
r ADMINISTRATIVE' CONTROLS
[
UNIT STAFF (Continued) 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 his deputy, or higher levels of management, in accordance with established procedures'and with documentation of the basis for granting i
the deviation.
Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designee to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
P i
i l
i SHOREHAM - UNIT 1 6-3
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THIS PAGE INTENTIONALLY DELETED.
3 1.
4 SHOREHAM'- UNIT 1 6-4 Amendment No. 2
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- s TABLE 6.2.2-1 MINIMUM SHIFT CREW COMPOSITION SINGLE UNIT FACILITY i
POSITION NUMBER OF INDIVIOUALS REQUIRED TO FILL POSITION CONDITION 1, 2, or 3 CONDITION 4 or 5 WE 1
1 SRO 1
None RO 2
1 E0 2
1 STA 1
None TABLE NOTATION WE - Watch' Engineer with a Senior Reactor Operators license on Unit 1.
SRO - Individual with a Senior Reactor Operators license on Unit 1.
R0 - Individual with a Reactor Operators license on Unit 1.
60 - Equipment Operator STA - Shift Technical Advisor Except for the Watch Engineer, the shift craw 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 accommodate unexpected absence-of on-duty shift crew members
.provided immediate action is taken to restore the shift crew com. position to within:the minimum requirements 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 Watch Engineer from the control room while the unit is in OPERATIONAL CONDITION 1, 2 or 3, an individual (other than the Shift Technical Advisor) with a valid Senior Reactor Operator license shall be desig-nated to assume the control. room command function.
During any absence of the Watch Engineer from the control room while the unit is in OPERATIONAL CONDITION 4 or 5, an individual with a valid Senior Reactor Operator license or Reactor Operator license shall be designated to assume the control room command function.
SHOREHAM - UNIT 1 6-5 t
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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 unit operating characteristics, NRC_ issuances, industry advisortes Licensee Event Reports, and other sources-of unit design and operating exper1ence information, including units of-similar design, which may indicate arcas for improving unit-safety.
The ISEG shall make detailed recommendations for revised procedures, equipment' modifications, maintenance activities, operations activities or other means of improving unit safety to the Manager, Nuclear Quality Assurance Department.
COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, multi-disciplined, full-time engineers located on site.
Each shall have a bachelor's-degree in engineering or related science, or equivalent, and at least 2 years professional experience in his field, at least 1 year of which experience shall be in the nuclear field.
RESPONSIBILITIES i
6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit i
activities to provide independent verification
- that these activities are per-i formed correctly and that human errors are reduced as much as practical.
{
RECORDS I
6.2.3,4 Records of activities performed by the ISEG shall be prepared, main-tained, and forwarded each calendar month to the Manager, Nuclear Quality 1
Assurance Department.
6.2.4 SHIFT TECHNICAL ADVISOR 1
6.2.4.1 The Shift Technical Advisor shall provide advisory technical support f
to the Watch Engineer in the areas of thermal hydraulics, reactor engineering,
-J and plant analysis _with regard to safe operation of the unit.
The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific j
or engineering disciplina and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit y
design and layout, including the capabilities of instrumentation and controls in the control room, t
- 6. 3 UNIT STAFF QUALIFICATI0_N,5 l
6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971 for comparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Health Physics Engineer who shall i
meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
Tne licensed Operators and Senior Operators shall also meet or exceed the mini-mum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.
- Not responsible for sign-off function.
SH0REHAM - UNIT 1 6-6 Amendment No. 2 i
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ADMINISTRATIVE CONTROLS s,
_ RESPONSIBILITIES (Continued)
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 c.
Operations and the Nuclear Review Board of disagreement between the ROC and the Plant Manager; however, the. Plant Manager shall have.
responsibility for resolution of such disagreements pursuant to Specification 6.1.1.
RECORDS 6.5.1.8 The ROC shall maintain written minutes of'each ROC meeting that, at a minimum, document the results of all ROC activities performed under the responsibility provisions of these Technical Specifications.
Copies shall be provided to the Vice President-Nuclear Operations and the Nuclear Review Board.
6.5.2 NUCLEAR REVIEW BOARD (NRB)
FUNCTION 6.5.2.1 The NRB shall function to provide independent review and audit of designated activities in the areas of:
a.
Nuclear power plant operations, b.
Nuclear engineering, c.
Chemistry and radiochemistry, d.
Metallurgy, e.
Instrumentation and control, f.
Radiological safety, g.
Mechanical and electrical engineering, and h.
Quality assurance practices.
The NRB shall report to and advise the Vice President-Nuclear Operations on l
those areas of responsibility in Specifications 6.5,2.7 and 6.5.2.8.
COMPOSITION 6.5.2.2 The NRB shall be composed of the permanent NRB Chairman and a minimum of five permanent NRB members.
The chairman-and all members of the NRB shall have qualifications that meet the requirements of Section 4.7 of ANSI /ANS.3.1-1978.
The membership shall include at least one individual from outside LILC0's or-its contractors' organizations and at least one individual with substantial BWR operating experience. The BWR operating experience may be provided by the individual who is from outside LILC0's or its contractors' organizations.
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the NRB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in NRB activities at any one time.
SHOREHAM - UNIT 1 6-9 Amendment No. 2 i
?
ADMXNISTRATIVE CONTQ0LS
+
h CONSULTANTS 6.5.2.4 provide expert advice to the NRB. Consultants shall be utilized as determined by I
MEETING FREQUENCY 6.5.2.5 The NRB shall meet at least once per calendar quarter during the 6 months thereafter. initial year of unit operation following fuel loading and at leas QUORUM 6.5.2.6 The quorum of the NRB necessary for the performance of. the NR8 review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least four but not less than one-half of the NRB members present including alternates.
of the quorum shall have line responsibility for operation of the unit.No more than a min REVIEW 6.5.2.7 The NRB shall review:
The safety evaluations for (1) changes to procedures, equipment or a.
systems and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question; b.
Proposed changes to. procedures, equipment, or systems which involve-an-unreviewed safety question as defined in 10 CFR 50.59; Proposed tests or experin,ents which involve an unreviewed safety c.
question as defined in 10 CFR 50.59; d.
Proposed changes to Technipal Specifications or this Operatirg License; Violations of codes, regulations, orders, Technical Specifications, e.
-license requirements, or of internal procedures or instructions having nuclear safety significance; f.
Significant operating abnormalities or deviations from normal and
[
expected performance of station equipment that affect nuclear safety; All REPORTABLE EVENTS; a.
All recognized indications of an unanticipated deficiency in some h.
aspect of design or operation of structures, systems, or components that could affect nuclear safety; and i.
Reports and meeting minutes of the ROC.
p SHOREHAM - UNIT 1 6-10 l
p r
ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8-Audits of station activities shall be pertcrmed under the cognizance of the NRB.
These audits shall encompass:
The conformance of station operation to provisions contained within a.
the Technical Specifications and applicable license conditions at least once per 12 months; b.
The performance, training and qualifications of the entire station staff at least once per 12 months; The results of actions taken to correct deficiencies occurring in c.
unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months; d.
The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least
(
once per 24 months; The fire protection programmatic controls including the implementing l
e.
procedures at least once per 24 months by qualified licensee QA l
personnel; j
f.
The fire protection equipment and program implementation at least.
once per 12 months utilizing either a qualified offsite licensee fire protection engineer (s) or an outside independent fire protection consultant.
An outside independent fire protection consultant shall be utilized at least every third year; g.
Any other area of station operation considered appropriate by the i
NRB, Vice President-Nuclear Operations or the Assistant Vice President-Nuclear Operations; h.
The radiological environmental monitoring program and the results thereof at least once per 12 months; i.
The 0FFSITE 00SE CALCULATION MANUAL and implementing procedures at least once per 24 months; and
'j.
The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes at least once per 24 months.
k.
The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 1
12 months.
RECORDS 6.5.2.9 Records of NRB activities shall be prepared, approved, and distributed as indicated below:
Minutes of each NRB meeting shall be prepared, approved, and forwarded f
-a, to the Vice President-Nuclear One ations and the Assistant Vice 1
President-Nuclear Operations within 14 days following each meeting.
b.
Reports of reviews encompassed by Specification 6.5.2.7 shall be prepared, approved, and forwarded to the Vice President-Nuclear Operations and the Assistant Vice President-Nuclear Operations within 14 days following completion of the review.
3 j
SHOREHAM - UNIT 1 6-11 Amendment No. 2
- - - - - - ~
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ADMINISTRATIVE CONTROLS
,,4
?
RECORDS (Continued)
Audit reports encompassed by Specification 6.5.2.8 shall be c.
'l forwarded to the Vice President-Nuclear Operations and the Assistant Vice President-Nuclear Operations and to the management positions responsible for the areas audited within 30 days after completion of J
the audit by the auditing organization.
- 6. 6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
1 The Commission shall be notified and a report submitted pursuant to a.
the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the ROC, and the results of this review shall be submitted to the NRB and the Vice President-Nuclear Operations.
- 6. 7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
The NRC Operations Center shall be notified by telephone as soon as a.
possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Vice President-Nuclear Operations and the NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the ROC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems, or structures, and (3) corrective action taken to prevent recurrence.
-The Safety Limit Violation Report sha M be submitted to the c.
Commission, the NRB, and the Vice President-Nuclear Operations within 14 days of the violation.-
d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
SHOREHAM - UNIT 1 6-12 Amendment No. 2 1