ML20097F672
| ML20097F672 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/08/1992 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20097F676 | List: |
| References | |
| NUDOCS 9206150467 | |
| Download: ML20097F672 (32) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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.i W ASHINGTON, D. C. 20555
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PUBLIC SERVICE ELECTRIC & GAS C0t'PANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No NPF-57 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The e,pplication for amendment filed by the Public Service Electric &
Gas Company (PSE&G) dated January 24, 1990, and supplemented on April 27, 1990, December 4, 1990, September 10, 1991 and December 10, Energy Act of 1954, as amended (the Act)quirements of the Atomic 1091, complies with the standards and re
, and the Commission's rules and regulations set for th 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 set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be nimical 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 Technial Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-57 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through tmendment No. 52, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PSE&G shall operate the facility in accordence with the Technical Specifications and the Environmental Protection Plan.
9206150467 920600 PDR ADOCK 05000354 P
3.
This license amendment is effective as of its date of issuance and shall be implemented within 90 days of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b
b Charles L. Miller, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuence: June 8, 1992
- ATTACHMENT TO LICENSE AMENDMENT NO 52 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following pages of the Appendix "A" Technical Specifications with i
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 XXiii XXiii*
XXIV XXIV
~
xxv xxv XXVi XXVi*
3/4 12-9 3/4 12-9 3/4 12-10 3/4 12-10 6-1 6-1*
6-2 6-2 6-5 6-5 66 6-6 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 6-15 6-15 6-16 6-16*
.6-17 6-17 6-18 6-18 6-19 6-19*
6-20 6-20 6-21 6-21 6-22 6-?2 6-23 6-23*
6-24 6-24 6-25 6-25
INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area and Map Defining Unrestricted Area and' Site Boundary for Radioactive Gaseous and Liquid Effluents..........
5-1 Figure 5.1.1-1 Exclusion Area and Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents..........................
5-2 Low Population Zone............................................
5-1 Figure 5.1.2-1 Low Population Zone.......................
5-3 5.2 CONTAINMENT Configuration..................................................
5-1 Design Temperature and Pressure................................
5-1 S e c o n d a ry C o n t a i nm en t..........................................
5-l 5.3 REACTOR CORE Fuel Assemblies................................................
5-4 Control Rod Assemblies.........................................
5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature................................
5-4 Vo1ume.........................................................
5-4
- 5. 5 METEOROLOGICAL TOWER LOCAT!0N..................................
5-4
- 5. 6 FUEL STORAGE ~
Criticality....................................................
5-5 Drainage.......................................................
5-5 Capacity...................................
5-5 5_._ 7 COMPONENT CYCLIC OR TRANSIENT LIMIT...........................
5-5 Table 5.7.1-1 Component Cyclic or Transient Limits........
5-6 HOPE CREEK xxiii -
INDEX
.A._D.MINISTRATIVE CONTROLS SE{ TION PAGE 6.1 sESP0NSIBILITY.................................................
6-1 6.2 ORGANIZATION...................................................
6-1 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS..........................
6-1 I
6.2.2 UNIT 6TAFF................................................
6-1 Figure 6.2.1-1 (Deleted)...........
6-3 Figura 6.2.2-1 (Deleted)................................
6-4 Figure 6.2.2-2 Minimum Shift Crew Composition Single Unit facility.....................
6-5 6.2.3 SHIFT TECHNICAL ADVIS0R...................................
6-6 6.3 UNIT STAFF QUALIFICATIONS......................................
6-6
-6.4 TRAINING.......................................................
6-6 6.5-REVIEW AND AUDIT..........................,....................
6-6 6.5.1 STATION OPERATIONS REVIEW COMMITTEE (50RC)...............
6-6 FUNCTION.-................................................
6-6 COMPOSITION..............................................
6-7 ALTERNATES...............................................
6-7 MEETING FREQUENCY-........................................
6-7 QU0RUM....................................................
6-7 RESPONSIBILITIES.........................................
6-7 REVIEW PR0 CESS............................................
6-8 AUTH0RITY.................................................
6-9 RECORDS AND REP 0RTS.......................................
6-9 HOPE CREEK xxiv Amendment No.52
INDEX ADMINISTRATIVE CONTROLS
- SECTION-PAGE 6.5.2 NUCLEAR SAFETY REVIEW AND AUDIT...........................
6-9 FUNCTION..................................................
6-9 COMPOSITION...............................................
6-9
. CONSULTANTS...............................................
6-10 0FFSITE-SAFETY REVIEW (0SR)...............................
6-10 FUNCTION........................
6-10 REVIEW....................................................
6-10 AUDITS....................................................
6-11 RECORDS AND REP 0RTS.......................................
6-1. )
ONSITE SAFETY REVIEW GROUP (SRG)..........................
6-12 FUNCTION..................................................
6-12 RESP 0NSIBILITIES..........................................
6-12 AUTH0RITY.................................................
6-]3 6.5.3 TECHNICAL' REVIEW AND CONTR0L..............................
6-13 ACTIVITIES................................................
'6 PROCEDURE RELATED 00CUMENTS...............................
6-13 NON-PROCEDURE RE LATED DOCUMENTS...........................
6-14 RECORDS AND REP 0RTS.......................................
6-14 1
1
- 6.6 REPORTABLE-EVENT ACTI0N........................................
6-14 6.7-SAFETY LIMIT VIOLATION.........................................
6-14
. 6.8 PROCEDURES AND PR0 GRAMS........................................
6-15 6.9 REPORTING REQUIREMENTS.........................................
6-17 6.9.1 ROUTINE REP 0RTd...........................................
6-17 STARTUP REP 0RT............................................
6-17 HOPE CREEK xxv Amendment No. 52
INDEX ADMINI5TRATIVE CONTROLS SECTION PAGE ANNUAL REP 0RTS............................................
6-17 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT........6 18 SEMIANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT....
6-19 MONTHLY OPERATING REP 0RTS.................................
6-20 CORE OPERATING LIMITS REP 0RT..............................
6-20 l
6.9.2 SPECIAL REP 0RTS...........................................
6-21 6.10 RECORD RETENTION..............................................
6-21 6.11 RADIATION PROTECTION PR0 GRAM..................................
6-22 6.12 HIGH RADIATION AREA...........................................
6-22 6.13 PROCESS CONTROL PROGRAM (PCP).................................
6-23
,6.14 0FFSITE DOSE CALCULATION MANUAL (00CM)........................
6-24 6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASEOUS, AND SOLID WA5TE TREATMENT SYSTEM5.................................
6-24 HOPE CREEK xxvi Amendment No. 34 DCT 2 01999 L
z TABLE 3.12.1-2 m
REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 2?
REPORTING' LEVELS x
Water Airborne Particulate Fish Milk Food Products Analysis (pCi/t) or Gasas (pCi/m )
(pCi/kg, wet).
(pCi/t)
(pCi/kg, wet) 3 H-3 30,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 w) Co-60 300 10,000 h Zn-65 300 20,000 m
Zr-Nb-95 400 I-131 2*
0.9 3
100 Cs-134 30
'10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200
.300 E
4 El-a 5
l
'g
- For drinking water samples.
This is a 40 CFR Part 141 value.
If no drinking water pathway exists, a value of 20 pCi/f may be used.
l TABLE 4.12.1-1 r
o DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (1)(2)
LOWER LIMIT OF DETECTION (LLD)I3)
Water Airborne Particulate Fish Milk Food Products Sediment Analysis (pCi/E) or Gas (pCi/m )
(pCi/kg, wet)
(pCi/t)
(pCi/kg, wet)
(pCi/kg, dry) 3 gross beta 4
0.01 H-3 3000 l
Mn-54 15 130 Fe-59 30 260 R
Co-58,60 15 130 a
30 260 y
Zn-65 Zr-Nb-95 15 I-131 1*
0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-1^0 15 15 E
B 5
"yj *LLD for drinking water samples.
If no drinking water pathway exists, a value of 10 pCi/t may be used.
l
6.0 ADMfNISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The' General Manager - Hope Creek 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 Senior Nuclear Shift Supervisor 6r 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 and Chief. Nuclear Officer shall be, reissued to all station l
personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsita organizations shall be established for unit operation and corporate management, respectively.
The onsite and offsite organizations shall include 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 management levels through, intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate in the form of organization charts, functional tions of departme'ntal responsibilities and rglationships,,a,descrip-nd job descriptions for key personnel positions, or in equivalent forts of documentation.
These requirements shall be documented in the Hope Creek Generating Station' Updated Final Safety Analysis Report and updated in accordance with 10 CFR 50.71(e),
b.
The General Manager - Hope Creek Operations shall be responsible for overall unit safe operation and shall have control over thase onsite activities necessary for safe ~ operation and maintenance of the plant, The Vice President and Chief Nuclear' Officer shall have corporate c.
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 health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizatio_nal freedom to ensure their independence from operating pressures.
UNIT STAFF 6.2.2* The unit organization shall be subject to the following:
a.
Each on duty shift shall.be composed of at least the minimum shift crew composition shown in Table 6.2.2-1; HOPE CREEK 6-1 Amendment No. 21 JAN 311389
\\
l-
- ADMINISTRATIVE CONTROLS-
=
UNIT STAFF (Continued) 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 OPERATIONAL-CONDITION 1, 2 or 3, at least one licensed Senior Reactor Operator shall be in the control room; c.
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 respon-sibilities during this operation; and d.
Administrative procedures shall be developed and implemented to limit the working hours of_ unit staff who perform safety-related functions u
e.g., licensed Senior Reactor Operators, licensed Reactor Operators, radiation protection technicians, equipment operators, and key main-tenance personnel.
Adequate shift coverage shall be maintaliied without routine heavy use of over-time.
The objective shall-be to have operating personnel work a nominal ** 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 shutdown for refueling, major maintenance on major unit modifications, on a temporary basis the following guidelines shall be followed:
1.'
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
2.
An. individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor tr:are 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 hours 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.
4.
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 appropriate department manager, or higher levels of management, in accordance with estab-lished procedures and.wi_th documentation of the basis for granting the devia-tion.
Controls shall be' included in the procedures such that individual over-
- time shall be reviewed monthly by the General Manager-Hope Creek Operations or
-his designee-to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
- The shift schedule is based upon a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shif t with a work week of either
-36' hours or 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.-
4- -
HOPE CREEK 6-2 Amendment No.52
TABLE-6.2.2-1 MINIMUM SHIFT CREW COMPOSITION SINGLE UNIT FACILITY POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITION 1, 2, or 3 CONDITION 4 or 5 SNSS*
1 1
NSS*
1 None NCO 2
1 E0 2
1 STA 1
None RPT 1
1 TABLE NOTATION SNSS - Senior Nuclear Shift Supervisor with a Senior Reactor Operator license on the Unit NSS
- Nuclear Shift Supervisor with a Senior Reactor Operator license on the Unit NCO
- Nuclear Control Operator with a Reactor Operatcr license on the Unit EO.
- Equipment.0perator STA
- Radiation Protection Technician Except'for the Senior Nuclear Shift Supervisor, the shift crew composition may be one less than the minimum requirements of Table 6.2.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members.provided immediate action is taken to restore the shift crew compo-sition to within the minimum requirements of Table 6.2.2-1.
This provision does not permit any shift crew position te be unmanned upon shift change due to an oncoming shift crewman being late or absent.
During any absence of the Senior Nuclear Shift Supervisor from the control room.
while the unit is in OPERATIONAL CONDITION 1, 2 or 3, an individual with a valid Senior Reactor Operator license shall be designated to assume the control room command function.
During any absence of the Senior Nuclear Shift Supervisor from the control room while the unit is in OPERATIONAL CONDITION 4 or 5, an individual with a valid Senior Reactor Operator license or Operator license shall be designated to assume the control room coinmand function.
- In cases where an' individual has a Senior Reactor Operator's license on the unit, is a qualified STA, and has a Professional Engineers License by virtue of successful completion of the Professional Engineer; examination or a bachelor's degree in.a scientific, engineering, or engineering technology discipline from an accredited institution, the individual can serve in a dual role capacity as either the SNSS/STA or NSS/STA.
(Note:
Foi those individuals with a bachelor's degree in a scientific or engineering technology discipline, course work must have included physical, mathematical, or engineering sciencc.)
Otherwise, there shall be a qualified STA as well as a SNSS and NSS on-shift.
HOPE CREEK 6-5 Amendment No.52
ADMINISTRATIVE-CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall provide advisory technical support to the Senior Nuclear Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the t:ni t.
The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific
- training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.
-6.3-UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI /ANS 3.1-1981 for comparable positions, except for the individual designated as.the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
The licensed Reactor Operators and Senior Reactor Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.
6.3.2 The Operations Manager, Operating Engineer,- Senior Nuclear Shif t Super-visors, and Nuclear Shift Supervisors, shall hold a senior reactor operator license.
The Nuclear Control Operators shall hold a reactor operator license.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager-Nuclear Training, shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI /ANS 3.1-1981 and 10 CFR Part 55.
l 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager - Site Protection and shall meet or exceed the require-ments of the SRP (NUREG-0800) Section 13.2,2.11.6, 10 CFR 50 Appendix R=and Branch Technical Position CMEB 9.5.1, Section C.3.d.
'6.5 REVIEW AND AUDIT
-6.5.1-STATION OPERATIONS REVIEW COMMITTEE (SORC)
' FUNCTION 6.5.1.1-The 50RC shail function to advise the General Manager - Hope Creek Operations on all matters related to nuclear safety.
HOPE CREEK 6-6 Amendment No. 52
ADMINISTRATIVE CONTROLS COMPOSITION
- 6. 5.1. 2 The 50RC shall be composed of the:
Chairman:
General Manager - Hope Creek Operations Member and Vice Chairman:
Operations Manager Member and Vice Chairman:
Technical Manager Member and Vice Chairman:
Maintenance Manager l
Member:
Maintenance Engineer Member:
Technical Engineer Member:
Radiation Protection /
Chemistry Manager Member:
Radiation Protection Engineer or Chemistry Engineer Member:
Onsite Safety Review Engineer Member:
Operating Enoineer ALTERNATES 6.5.1.3 All alternate members shall be arcointed in writing by the 50RC Chairman.
Only designated Vice Chairmen or the General Manager - Hope Creek a.
Operations may act as Chairman of a 50RC meeting.
b.
No more than two alternates to members shall participate as voting members in 50RC activities at any one meeting.
Alternate appointees will only represent their respective department.
c d.
Alternates for members will not make up part of the voting quorum when the member the alternate represents is also present.
MEETING FREQUENCY 6.5.1.4 The 50RC shall meet at least once per calendar month and as convened by the 50RC Chairman or his designated alternate.
QUORUM
- 6. 5.1. 5 The quorum of the 50RC necessary for the performats.e of the 50RC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least four members including alternates.
RESPONSIBILITIES 6.5.1.6 The 50RC shall be responsible for:
a.
Review of:
(1) Upper tier administrative procedures within the scope of Regulatory Guide 1.33 (2/78), and changes thereto and (2) Newly created procedures or changes to existing HOPE CREEK 6-7 Amendment No.52
ADMINISTRATIVE CONTROLS procedures that require a 10 CFR 50.59 safety evaluation as described l
in Section 6.5.3.2.d.
b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to Appendix "Ad Technical Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
Review of the safety evaluations that have been completed under the i
e.
provisions of 10 CFR 50.59.
f.
Initiation or review of investigations of all violations of the Tech-nical Specifications including the reports covering evaluations and recommendations to prevent recurrence.
g.
Review of all REPORTABLE EVENTS.
h.
Review of facility operations to detect potential nuclear safety hazards.
i.
Performance of special reviews, investigations or analyses and reports thereon as determined by the 50RC.
l j.
Review of the Facility Security Plan and implementing procedures and changes thereto that require a 10 CFR 50.59 safety evaluation, or involve a potential decrease in the effectiveness of the plan, per 10 CFR 50.54(p).
k.
Review of the Facility Emergency Plan and implementing procedures and changes thereto that require a 10 CFR 50.59 safety evaluation, or involve a potential decrease in the effectiveness of the plan, per 10 CFR 50.54(q).
1.
Review of the Fire Protection Program and implementing procedures and changes thereto that require a 10 CFR 50.59 safety evaluation.
l m.
Review of all unplanned on-site releases of radioactivity to the environs including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent l
recurrence.
n.
Review of changes to the PROCESS CONTROL MANUAL and the OFF-SITE DOSE CALCULATION MANUAL.
l REVIEW PROCESS 6.5.1.7 A technical review and control system utilizing qualified reviewers shall function to perform the periodic or routine review of procedures and changes-thereto.
Details of this technical review process are provided in Section 6.5.3.
HOPE CREEK 6-8 Amendment No. 52 j
y.
ADMINISTRATIVE CONTROLS AUTHORITY
- 6. 5.1. 8 The SORC shall:
Provide recommendations in writing to the General Manager - Hope Creek a-Operations indicating approval or disapproval of items considered under Specification'6.5.1.6 prior to their imphmentation, b.
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 and Chief Nuclear Officer and to the General Manager - Quality Assur-ance and Nuclear Safety of disagreement between the 50RC and the General Manager - Hope Creek Operations; however, the General Manager - Hope Creek Operations shall have responsibility for resolution of such disagreements pursuant to Specification'6.1.1.
RECORDS AND REPORTS
- 6. 5.1. 9 The SORC shall maintain minutes of each SORC meeting, and copies shall be provided to the Vice President and Chief Nuclear Officer, General Manager -
Quality Assurance and Nuclear Safety and Manager - Nuclear Safety.
6.5.2-NUCLEAR SAFETY REVIEW AND AUDIT FUNCTION 6.5.2.1 The Nuclear Safety Department shall function to provide the indepenuent l
safety review program and audit of designated activities.
COMPOSITION 6.5.2.2 The Nuclear Safety Department, under the cognizance of the General Manager - Quality Assurance and Nuclear Safety, shall consist of the Manager - Nuclear Safety, the Offsite Safety Review staff (OSR) and the Onsite Safety Review Group _ (SRG).
The OSR staff and the SRG each consist of at least four dedicated, full-time engineers.
The Manager - Nuclear Safety and the Offsite Safety Review staff shall meet or l
exceed the qualifications described in Section 4.7 of ANS 3.1 - 1981 and shall
-be guided by the provisions for independent review described in Section 4.3 of ANSI N18.7-- 1976 (ANS 3.2).
The Offsite Safety Review staff shall generally possess experience and competence in the areas listed in Section 6.5.2.4.1.. A system of qualified reviewers from other technical organizations shall be utilized to augment OSR staff expertise in the disciplines of Section 6.5.2.4.1, where appropriate.
Such qualified re:' ewers shall meet the same qualification requirements as the
'Offsite Safety Review staff, and shall not have been involved with performance of the original work.
The Onsite Safety Review Group staff shall meet or exceed the qualifications described in Section 4.4 of ANS 3.1 - 1981.
HOPE CREEK 6-9 Amendment No. 52
w ADMINISTRATIVE CONTROLS CONSULTANTS 6.5.2.3. Consultants or other technical experts shall be utilized by the Nuclear Safety Department as needed.
6.5.2.4 0FFSITE SAFETY REVIEW (OSR)
FUNCTION 6.5.2.4.1 The OSR staff shall_ function to provide independent review and a!,:t l
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 engineering, h.
Electrical engineering 1.
Quality assurance j.
Nondestructive testing k.
Emergency preparedness REVIEW 6.5.2.4.2 The OSR staff shall review:
a.
The safety evaluations for changes to procedures, equipment, or systems; and 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 and tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; c.
Proposed changes to Technical Specifications or this Operating License; d.
Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; e.
Significant operating abnormalities or deviations from normal and expected performance of facility equipment that affect nucl;ar safety; HOPE' CREEK 6-10 Amendment No. 52
ADMINISTRATIVE CONTROLS f.
All REPORTABLE EVENTS.-
- g. -
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and h.
Reports and meeting minutes of the 50RC.
AUDITS 6.5.2.4.3 Audits of facility activities -hall be performed under the cognizance of the OSR staff.
These audits shall encompass:
l a.
The conformance of facility 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 facility staff at least once per 12 months; c.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months; d.
The performance of activities required by the Operational Quality Assurance Program to meet =the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months; e.
The Facility Emergency Plan and implementing procedures at least once per 12 months; f.
The Facility Security Plan and implementing procedures at least once per 12 months; g.
Any other area of facility operation considered appropriate by the General Manager - Quality Assurance and Nuclear Safety or-the Vice l
President and Chief Nuclear Officer;
-- h.
The facility Fire Protection Program and the implementing procedures at least once per 24 months; 1.
Thel fire protection and loss prevention program implementation at least once per 12 months utilizing either a qualified off-site licensee fire' protection engineer (s) or an outside independent fire protection consultant.
An outside independent fire protection con-sultant shall be utilized at least once per 36 months; and
-j.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
k.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; HOPE CREEK 6-11 Amendment No. 52
._~
=ADMINISTRATTVE CONTROLS 1.
The PROCESS CONTROL PROGRAM and implementing procedures for process-ing and packaging of radioactive wastes at least once per 24 months;
- _and, The performance of activities required by the Quality Assurance Program m.
for effluent and environmental monitoring at least once per 12 months.
The above audits may be conducted by the Quality Assurance Department or an l
independent consultant.
Audit plans and final audit reports shall be reviewed by the OSR staff.
l RECORDS.AND-REPORTS l
6.5.2.4.4 Records of OSR activities shall be. maintained.
Reports of reviews and audits _shall be prepared and distributed as indicated below:
a.
The results of reviews performed pursuant to Section 6.5.2.4.2 shall be reported to the Vice President and Chief Nuclear Officer at least l
- monthly, b.
Audit reports prepared pursuant to Specification 6.5.2.4.3 shall be forwarded by the auditing organization to the Vice President and Chief Nuclear Officer and to the management positions responsible for the areas audited (1) within 30 days after completion of the audit for those audits conducted by the Quality Assurance Department, and l
(2) within 60 days after completion of the audit for those audits conducted by an independent consultant.
6.5.2.5 ONSITE SAFETY REVIEW GROUP (SRG)
FUNCTION 6.5.2.5.1 The SRG shall function to provide: the review of plant design and
-operating experience for potential opportunities to improve plant safety; evalua-tion of plant operations and maintenance activities; and advice to management on the overall quality and safety of plant operations.
The SRG shall make recommendations for revised procedures, equipment modifica-
~
tions, or other means of improving plant safety to appropriate station / corporate management.
RESPONSIBILITIES 6.5.2.5.2 The-SRG shall be.respons_ible for:
a.
Review of selected plant operating characteristics, NRC issuances, industr
- advisories, and other appropriate sources of plant design and op..ating exnerience information which may indicate areas for improving _ plant safety.
b.
Review of selected facility features, equipment, and systems.
c.
Review of selected procedures ano plant activities including main-tenance, modification, operational problems, and operational HOPE CREEK 6-12 Amendment No. 52
ADMINISTRATIVE-CONTROLS d.
Surveillance of selected plant operations and maintenance activities to provide independent verification
- that they are performed correctly and that human errors are reduced to as low as reasonably achievable.
AUTHORITY 6.5.2.6 The Nuclear Safety Department shall report to and advise the Vice Pres-l ident and Chief Nuclear Officer on those areas of responsibility specified in Sections 6.5.2.4 and 6.5.2.5.
6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 All programs and procedures required by Technical Specification 6.8 and changes thereto, and any other proposed procedures or changes thereto, which affect plant nuclear safety as determined by the General Manager - Hope Creek Operations, other than editorial or typographical changes, shall be reviewed as follows:
PROCEDURE RELATED DOCUMENTS 6.5.3.2 Procedures, Programs and changes thereto shall be reviewed as follows:
a.
Each newly created procedure, program or change-thereto shall be independently reviewed by an individual knowledgeable in the area affected other than the individual who prepared the procedure, pro-gram 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-Station Administrative procedures will-be approved by the appropriate station Department Manager or by the General Manager - Hope Creek Operations.
Each station Department Manager shall be responsible for a pre-designated class of procedures.
The General Manager - Hope Creek Operations shall approve Station Administrative Procedures, Security Plan _ implementing procedures and Emergenc Plan implementing procedures, b.
Or.-the-spot changes to procedures which clearly do not change the intent of the approved procedures shall be approved by two members of the plant management staff,-at least one of whom holds a Senior Reactor Operator's License.
Revisions to procedures which may involve a change in intent of the approved procedures, shall be reviewed in accurdance with Section 6.5.3.2.a above.
c.
Individuals responsible for reviews performed in accordance with item 6.5.3.2.a above shall be approved by the SORC Chairman and designated as a Station Qualified Reviewer.
A system of Station Qualified Reviewers shall be maintained by the 50RC Chairman.
Each review shall include a written determination of whether or not additional
- Not responsible for sign-off function.
HOPE CREEK 6-13 Amendment No. 52
i ADMINISTRATIVE CONTROLS cross-disciplinary review is necessary.
If deemed necessary, such review shall be performed by the appropriate designated review personnel.
The Station Qualified Reviewers shall meet or exceed the qualifications described in Section 4.1 and 4.7 of ANS 3.1, 1981.
d.
If the Department Manager. determines that the documents involveo require a 10 CFR 50.59 safety evaluation, the documents shall be for-warded for 50RC review and also to the OSR staff for an independent review to determine whether or not an unreviewed safety question is involved.
Pursuant to 10 CFR 50.59, NRC approval of items involving unreviewed safety questions or requiring Technical Specification changes shall be obtained prior to implementation.
NON-PROCEDURE RELATED DOCUMENTS 6.5.3.3 Tests or experiments, and changes to equipment or systems shall be forwarded for 50RC review and also to the OSR staff for an independent review t< determine whether or not an unreviewed safety question is involved.
The results of the OSR staff reviews will be provided to SORC.
Recommendations for approval are made by SORC to the General Manager - Hope Creek Operations.
Pursuant to 10 CFR 50.59, NRC approval of items involving unreviewed safety questions or requiring Technical Specification changes shall be obtained prior to implementation.
RECORDS AND REPORTS 6.5.3.4 Written records of reviews performed in accordance with item 6,5.3.2a above, including recommendations for approval or disapproval, shall be maintained.
Copies shall be provided to the General Manager - Hope Cree'. Operations, 50RC, the OSR staff, and/or NRC as necessary when their reviews are required.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions chall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified pursuant to the requirements of Section 50.72 to 10 CFR Part 50 and a report submittal pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the 50RC, and the results of this review shall be submitted to the OSR staff and the Vice President and Chief Nuclear Officer.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
8 I
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Vice President and Chief
{
"sclear Of ficer and the General Manager - Quality Assurance and Nuclear Safety shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
HOPE CREEK 6-14 Amendment No.52 8
ADMINISTRATIVE CONTROLS b.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the SORC.
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.
c.
The Safety Limit Violation Report shall be submitted to the Commission, the General Manager - Quality Assurance and Nuclear Safety and the l
Vice President and Chief Nuclear Officer within 30 days of the violation.
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,- Revis'.on 2, February 1978.
b.
The applicable procedures required to implement the requirements of NUREG-0737 and supplements thereto.
c.
Refueling operations.
d.
Surveillance and test activities of safety-related equipment, e.
Security Plan implementation, f.
Emergency Plan implementation, g.
Fire' Protection Program implementation.
h.
PROCESS CONTROL PROGRAM implementation.
1 0FFSITE 00SE CALCULATION MANUAL implementation, j.
Quality Assurance Program for effluent and environment monitoring.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed and approved in accordance with specification 6.5.1.6
-or 6.5.3, as appropriate, prior to-implementation and reviewed periodically as set forth in: administrative procedures.
6.8.3 On-the-Spot changes to procedures of Specification 6.8.1 may be made provided:
a.
The intent of the original procedure is not altered;
-b.
The change is approved by two members of the unit management staff, at least one of whom holds a Senior Reactor Operator licerse on the unit affected; and HOPE CREEK 6-15 Amendment No. 52 1
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
The change is documented and receives the same level of review and c.
approval as the original procedure under Specification 6.5.3.2a within 14 days of implementation.
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 HPCI, CS, RHR, RCIC, Containment Hydrogen Recom-biner, H /Os analyzer, Post-Accident Sampling, Control Rod Drive 2
Hydraulic (Scram Discharge portion) systems.
The program shall include the following:
1.
Preventive maintenance and periodic visual inspection requirements, and 2.
A sarvice pressure leak test fo: each system at refueling cycle intervals or less.
b.
In-Plant Radiation Monitorino A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.
This program shall include the following:
1.
Training of personnel, 2.
Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment.
c.
Post-accident Sampling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous efflu-ents, and_ containment atmosphere samples under accident conditions.
The program sh'all include the following:
1.
Training of personnel, 4
2.
Procedures for sampling and analysis, and 3.
Provisicns for maintenance of sampling and analysis equipment l
HOPE CREEK 6-16 l
_ - - - -. ~ _
s t
?
ADMINISTRATIVE CONTROLS l
t
- 6. 9 REPORTING REQUIREMENTS ROUTINE REPORTS 1
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 USNRC Administrator, Region 1, 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 i
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 unit.
- 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 opera-
-tion 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 r:omple-
-tion of the startup test program, (2) 90 days following resumption or commence-ment of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the startup report does not covo all three events (i.e., initial criticality, completion of startup test pre ram, i.~.d resumption or commencement of commercial operation) supplementary r4 orts 5.all be submitted 4
at least every 3 months until all three events have beer r^mp M eu.
ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous c.alendar year shall be submitted prior to March 1 of each year.
l
- 6. 9.1. 5 Reports required on an annual basis shall include:
A tabulation on an annual basis of the number of station, utility, a.
and other-personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according tc work and job functions ** (e.g., reactor operations and surveillance,
- A single submittal may be made for multiple unit station.
The submitta's should combine those sections t!-4 are comnon w all units at the station.
- This tabulation supplements the requirements of S20.407 of 10 CFR Part 20.
HOPE CREEK 6-17 Amendment No.52
l t
I ADMINISTRATIVE CONTROLS inservice inspection, routine maintenance, special maintenance i
[ describe maintenance), waste processing, and refueling).
The dose t
assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dasimeter (TLD), or self '^ading dositneter l nasurements.
Small exposures totalling less than 20% of the indiv-idual total dose need not be accounted for.
In the aggregate, at least i
80% of the total whole-body dose received from external sources should be assigned to specific major work functions; and b.
Documentation of all challenges to main steamline safety / relief valves.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6. 9. *4. 6 Routine radiological environmental operating reporting covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
The initial report shall be submitted prior to 3
May 1 of the year following initial criticality.
The annual radiological environmental operating reports shall include summaries, i
interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a com-parison 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 Specification 3.12.2.
If harmful ef fects or evidence of irreversible damage are detected by the monitoriN, 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.
Deviations from the sampling program identified in Technical Specification 3.12.1 shall be reported.
In the event that some results are not available for inclusion with the reports, 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; at least two legible maps, one covering sampling locations near the SITE BOUNDARY, and a second covering the more distant locations, all keyed to a table giving distances and directions f rom one reactor; and the results of licensee participation in the Interlabor-atory Comparison Program, as required by Specification 3.12.3.
The report-shall also include the results of specific activity analysis in which. the primary coolant exceeded the limits of Specification 3.4.5.
The following_information shall be included:
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> e ior to the first sample in which the limit was exceeded; (2) Results r
of the last isotopic analysis for radioiodine performed prior to exceeding the limit, result's of analysis while limit was exceeded and results of one analysis HOPE CREEK 6-18 Amendment No. 52
l ADMikiSTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRO
- ENTAL OPERATING REPORT (Continued) after the radiciodine activity was esduced to less thra limit.
Each result
~
should include date snd time of sampling and the radiciodine concantrations; (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 1131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and ($)
The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.7 Routineradioactivereltdsereportscoveringtheoperationofthe unit during the previous 6 months of operation shall be submit'ed within 60 days af ter January 1 and July 1 of each year.
The period of the first report sha))
begin with the date of initial criticality.
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, %asuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid.
and Gaseous Effluents from Light Vater-Cooled Ruclear Power Plants," ltavision 1 June 1974, with data summarized on a quarterly basis following the* format of Appendix B thereof.
The radioactive affluent release report to be subsitted 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 for1a of an hour-by-hour listing of wind speed, wind direction, and atmos-pharic stability, and precipitation (if measured) on magnetic tape, or in the fors of joint frequency distributions of wind speed, wind direction, and atmos-pheric stability. This same report shall include an assessment of the radia-tien doses due to the radioactive liquid and gaseous offluents 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 affluents to MOSElls 0F THE PUBLIC due to their activities inside tt.a SITE BOUNDARY (Figure 5.1.1-1) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and locatio', sh411 be included in these reports.
The historical annual average noteor91ogy or the meteorological conditions concurrent with the time of releast ot n dicectivw materials in gaseous effluents (as determined by sampling frequeicy and measurement) shall be used for determining the gaseous pathway doses.
The assessment of radiation doses shall be performed in accordance with he CFFSITE DOSE CALCULATION MANUAL (00CM). The Seelan'nual Radioactive Eff'sent Release Report shall identify those radiological environnantal sample paracters and locations where it is not possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.
In addition, the cause of the unavailability of samples for the pathway and th i new location (s) for obtaining replacement samples should be identified.
Th a report should also include a revised figure (s) and table (s) for the 00CM rt flecting the new location (s).
HOPE CREEK 6-19
l
@MINISTRATIVECONTROLS SEMIANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT (Continnd)
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 path-i ways and direct radiation) for the previous 12 consecutive montas to show con-formance 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, Rev. 1.
The rad W tive effluents release shall include the following information for each c' un 4 f solid waste (as defined by 10 CFR 61) shipped offsite during the report gM ;ud:
- a..
Centainer volume, i
b.
Total curie quantity (specify whether determined by measurement or estimate),
Principal radionuclide (specify whether determined by measurement c.
or estimate),
d.
Type of waste (e.g., spent resin, compact dry waste, evaporator bottoms),
Type of container (e.g., LSA, Type A, Type 8, large Quantity), and e.
t f.
Solidification agent (e.g., cement, urea formaldehyde).
The radioactive effluent release reports shall include unplanned releases from the site to the UNRESTRICTED AREA of radioactive materials in gaseous and liquid effluents on a quarterly basis.
The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP), OFFSITE DOSE CALCULATION MANUAL (0DCM) or radio-active waste systems made during the reporting period.
MONTHLY OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Docu-ment Control Desk, Washington, D.C. 20555, with a copy to the USNRC Administrator, Region 1, no later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITS REPORT 6.9.1.9 Core operating limits shall be established and documented in the PSE&G generated CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following Technical Specifications:
3/4.2.1 AVERAGE PLANAR LINEAR. HEAT GENERATION RATE 3/4.2.3 MINIMUM CRITICAL POWER RATIO
.3/4.2.4 LINEAR HEA* GENERATION RATE l
HOPE CREEK 6-20 Amendment No. 52 i
ADMINISTRATIVE COIJROLS CORE OPERATING LIMITS REPORT (Continued)
The analytical methods u'ed to determine the core operati g limits shall be those previously reviewed and approved by NRC in NEDE-24011-P-A (the latest approved revision), General Electric Standard Application for Reactor Fuel (GESTAR II).
The co 3 operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and 'ransient and accident analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supple-ments thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident inspector.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, DC 20555, with a copy to the USNRC Administrator, Region 1, within the time period specified for each report.
6.9.3 Violations of the requirements of the fire protection program described in the Final Safety Analysis Report which woeld have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be submitted to the U.S. Nuclear Regulatory Commissien, Document Control Desk, Washington, DC 20555, with a copy to the USNRC Administrator, Region 1, via the l
Licensee Event Report System within 30 days.
,6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
SPECIAL REPORTS 6.10.2 The following records shall be retained for at least 5 years:
a.
Records and logs of unit operation covering time interval at each power level.
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, e.
Records of changes made to the procedures required by Specification 6.8.1.
f.
Records of radioactive shipments, g.
Records of sealed source and fission detector leak tests and rese'ts.
HOPE CREEK 6-21 Amendment No. 52
ADMINISTRATIVE CONTROLS _
RECORD RETENTION (Continued) h.
Records of annual physical inventory of all sealed source material of record.
6.10.3 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, Records of transient or operational cycles for those unit components e.
identified in Table 5.7.1-1.
f.
Records of reactor tests and experiments, g.
Records of training and qualification for current members of the unit
- staff, b.
Records of inservice inspections performed pursuant to these Technical Specifications.
i.
Records of quality assurance activities required by the Quality Assurance Program.
j.
Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of SORC-meetings and OSR activities.
l 1.
Records of the snubber service life monitoring pursuant to Technical Specification 4.7.5.
m.
Records of analyses required by the radiologit.a1 environmental monitoring program which would permit evaluation of the accuracy of thc-analyses at a later date.
This should include procedures effective at specified times and QA records showing that these procedures were followed.
6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, main-tained, and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA
'6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20,203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity HOPE CREEK 6-22 Amendment No,52
l 4
ADMINISTRATIVE CONTROL >
HlGH RADIATION AREA (Continued) 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 grou9 of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation aonitoring device which continuously indicates the radia-a.
tion dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the done rate levels in the area have been established and personnel have been made knowledgeable of them.
A radiation protecticn qualified individual (i.e., qualified in c.
radiation protection procedures) with a radiation dose rate monitor-ing 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 Radiation Protection Supervisor in the RWF.
6.12.2 In addition to the requirements of Specification 6.12.1, areas access-ible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose greater than 1000 mrem
- shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Senior Nuclear Shift Supervisor on duty and/or the radiation protection supervision.
Doors shall remain locked except during periods of access by personnel under an approved RWP wh.ch shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.
For individual areas accessible to personnel withradiationlevelssuchthatamajorportionofthebodycouldreceivein 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrem that are located within large areas, such as the containment, where no enclosure exists for purposes of locking,, and no enclosure can be reasonably constructed around the 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, continuous surveillance direct or remote (such as use of closed circuit TV cameras), may be made by personnel qualified in radiation protection proce-dures 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.
" Measurement made at 18 inches from source of radioactivity.
- Radiation protection personnel or personnel escorted by radiation protection personnel shall be exempt from the RWP issuance requirement during the per-formance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.
i HOPE CREEK 6-23 Amendment No. 34 OCT 2 0 ISO
4 ADMINISTRATIVE CONTRCLS PROCESS CONTROL PROGRAM (PCP) (Continued) 6.13.2 Licensee initiated changes to the PCP:
1.
Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was
- made, lhis submittal shall contain:
a.
Suf ficien',1y detailed information to totally support the rationale for the change without benefit of additional or supplemental information; 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 c.
Documentation of the fact that the change has been reviewed and found acceptable by the 50RC.
7 2.
Shall become effective upon review and acceptance by the 50RC.
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee initiated changes to the ODCM:
1.
Shall be submitted to the Commission in the Semiannual Radioactive Ef fluent Release Report for the period in which the change (s) was made.
This submittal shall contain:
a.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supple-mental 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 appropriate 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 determination; and c.
Documentation of the fact that the change has been reviewed and found acceptable by the 50RC.
2.
Shall become effective upon review and acceptance by the 50RC.
6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.15.1 Licensee initiated major changes to the radioactive waste system (liquid, gaseous and solid):
1.
Shall be reported to the Commission in the UFSAR for the period in l
which the evaluation was reviewed by 50RC.
The discussion of each change shall contain:
l HOPE CREEK 6-24 Amendment No. 52 l
ADMINISTRATIVE CONTROLS MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT M MS (Continued)
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a.
A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; I
b.
Sufficient _ detailed information to totally support the reascn 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 differ f rom those previously predicted in the license application and amendments thereto; e.
An evaluation of the change, which shows the expected maximum 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 50RC.
2.
Shall become effective upon review and acceptance by the 50RC.
HOPE CREEK 6-25 Amendment No. 52
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