ML20236S011
| ML20236S011 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/13/1998 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20236S013 | List: |
| References | |
| GL-89-01, GL-89-1, NUDOCS 9807240081 | |
| Download: ML20236S011 (26) | |
Text
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UNITED 8TATES
.gJ' NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D.C. age 0640M l
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCI FAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE
' Amendment No.184 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated April 24,1996, as supplemented December 15,1997, and June 22,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
' B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
' E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
i 9907240081 990713 PDR ADOCK 05000266 P
r
. 2.
Accordingly, the license is amended to approve the relocation of certain Technical Specification requirements to licensee-controlled documents, as described in the licensee's application dated April 24,1996, as supplemented by letter dated December 15,1997, and June 22,1998, and evaluated in the stars safety evaluation dated July 13',1998. This license is also hereby amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-24 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 184, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from the date of issuance.
Implementation shall also include relocation of certain Technical Specification requirements to licensee-controlled documents, as described in the licensee's application dated April 24,1996, as supplemented by letter dated December 15,1997, and June 22,1998, and evaluated in the stafs safety evaluation attached to this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION Linda L. Gundrum, Project Manager Project Directorate 111-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance: July 13, 1998
't UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 6
...../
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.188 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated April 24,1996, as supplemented on December 15,1997, and June 22,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; l
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
I
. 2.
Accordingly, the license is amended to approve the relocation of certain Technical Specification requirements to licensee-controlled documents, as described in the licensee's application dated April 24,1996, as supplemented by letter dated December 15,1997, and June 22,1998, and evaluated in the staff's safety evaluation dated July 13,1998. This license is also hereby amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-27 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 188, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from the date of issuance, implementation shall also include relocation of certain Technical Specification requirements to licensee-controlled documents, as described in the licensee's applicat5n dated April 24,1996, as supplemented by letter dated December 15,1997, and June 22,1998, and evaluated in the staff's safety evaluation attached to this amendn. ant.
FOR THE NUCLEAR REGULATORY COMMISSION Linda L. Gundrum, Project Manager Project Directorate lil-1 Division of Reactor Projects -Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance: July 13, 1998 LL___---_--_---_----------_-----------.----
d.
ATTACHMENT TO LICENSE AMENDMENT NO. 184 TO FACILITY OPERATING LICENSE NO. DPR-24 AND LICENSE AMENDMENT NO.188 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Specifications by removing the pages identifMKi below and inserting the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT TS 15-1 TS 15-1 TS 15-li TS 15-li TS 15.3.9-1 TS 15.3.g-1 TS Table 15.4.1-1 (page 5 of 6)
TS Table 15.4.1-1 (page 5 of 6)
TS 15.4.10-1 TS 15.4.10-1 TS 15.6.5-3 TS 15.6.5-3 TS 15.7.1-1 thru TS 15.7.1-3 TS 15.7.1-1 TS 15.7.2-1 TS 15.7.2-1 TS Figure 15.7.1-1 TS 15.7.2-2 (Figure 16.7.2-1)
TS 15.7.3-1 thru 15.7.3-7 TS 15.7.3-1 TS 15.7.4-1 TS 15.7.4-1 TS Table 15.7.4-1 TS Table 15.7.4-2 (2 pages)
Notations for Tables 15.7.4-1 and 15.7.4-2 TS 15.7.5-1 thru TS 15.7.5-8 TS 15.7.5-1 TS 15.7.6-1 TS 15.7.6-1 TS Table 15.7.6-1 Notes for Table 15.7.6-1 TS Table 15.7.6-2 Notes for Table 15.7.6-2 TS 15.7.7-1 thru TS 15.7.7-4 TS 15.7.7-1 TS Table 15.7.7-1 (2 pages)
TS Table 15.7.7-2 Notes for Table 15.7.7-2 TS Table 15.7.7-3 s
TS 15.7.8-1 thru TS 15.7.8-6 TS 15.7.8-1 thru 15.7.8-7 I
TABLE OF CONTENTS Section Big Eage 15 TECHNICAL SPECIFICATIONS AND BASES 15.1 Definitions 15.1-1 15.2.0 Safety Limits and Limiting Safety System Settings 15.2.1-1 15.2.1 Safety Limit, Reactor Core 15.2.1-1 15.2.2 Safety Limit, Reactor Coolant System Pressure 15.2.2-1 15.2.3 Limiting Safety System Settings, Protective Instrumentation 15.2.3-1 15.3-
. Limiting Conditions for Operation 15.3.0-1 15.3.0 General Consideration 15.3.0-1 15.3.1 Reactor Coolant System 15.3.1-1 15.3.2 Chemical and Volume Control System 15.3.2-1 15.3.3 Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and Containment Spray 15.3.3-1 15.3.4 Steam and Power Conversion System 15.3.4-1
{
15.3.5 Instrumentation System 15.3.5-1 15.3.6 Containment System 15.3.6-1 15.3.7 Auxiliary Electrical Systems 15.3.7-1 I
15.3.8 Refueling 15.3.8-1 15.3.9 Emuent Releases 15.3.9-1 15.3.10 Control Rod and Power Distribution Limits 15.3.10-1 15.3.11 Movable in-Core Instrumentation 15.3.11-1 15.3.12 Control Rovm Emergency Filtration 15.3.12-1 15.3.13 Shock Suppressors (Snubbers) 15.3.13-1 15.3.14 Fire Protection System (This section was deleted as of 1/8/97) 15.3.14-1 15.3.15 Low Temperature Overpressure Protection System 15.3.15-1 15.3.16 Reactor Coolant System Pressure isolation Valves 15.3.16-1 15.4 Surveillance Requirements 15.4-1 15.4.1 Operational Safety Review 15.4.1-1 15.4.2 in-Service Inspection of Safety Class Components 15.4.2-1 15.4.3 Primary System Testing Following Opening 15.4.3-1 15.4.4 Containment Tests 15.4.4-1
-15.4.5 Emergency Core Cooling System and Containment Cooling
- System Tests 15.4.5-1 15.4.6 Emergency Power System Periodic Tests 15.4.6-1 15.4.7 Main Steam Stop Valves 15.4.7-1 15.4.8 Auxiliary Feedwater System 15.4.8-1 l
15.4.9 Reactivity Anomalies 15.4.9-1
.15.4.10 Radiological Environmental Monitoring 15.4.10-1 l
15.4.11 Control Room Emergency Filtration 15.4.11-1 l
l 15.4.12 Miscellaneous Radioactive Materials Sources 15.4.12-1 j
(
'15.4.13 Shock Suppressors (Snubbers) 15.4.13-1 l
15.4.14 Surveillance of Auxiliary Building Crane Lifting Devices 15.4.14 )
15.4.15 Fire Protection System (This section was deleted as of 1/8/97) 15.4.15-1 i
u.4.16 Reactor Coolant System Pressure isolation Valves Leakage Tests 15.4.16-1 l
15-1 Unit 1 - Amendment No. 06,470,472,184 Unit 2 - Amendment No. 400,444,446,188 j
u..
TABLE OF CONTENTS (Continued)
Section Tjilm Eage 15.5 Design Features 15.5.1-1 15.5.1 Site 15.5.1-1 15.5.2 Containment 15.5.2-1 15.5.3 Reactor 15.5.3-1 15.5.4.
Fuel Storage, 15.5.4-1 15.6 Administrative Controls 15.6.1/2-1 15.6.1 Responsibility 15.6.1/2-1 15.6.2 Organization 15.6.1/2-1 15.6.3 Facility Staff Qualifications 15.6.3/4/5-1
'15.6.4 Training
-15.6.3/4/5-1
'15.6.5 Review and Audit 15.6.3/4/5-1 15.6.6 Reportable Event Action 15.6.6-1 15.6.7 Action To Be Taken if A Safety Limit is Exceeded 15.6.7-1 15.6.8 Plant Operating Procedures 15.6.8-1 15.6.9 Plant Reporting Requirements 15.6.9-1 15.6.10 Plant Operating Records 15.6.10-1 15.6.11 Radiation Protection Program 15.6.11-1 1
15.7 Radiological Effluent Technical Specifications (RETS) 15.7.1.
Definitions 15.7.1.I 15.7.2 Site Description 15.7.2-1 15.7.3 Radioactive Effluent Monitoring instrumentation Operability Requirements 15.7.3-1 15.7.4 Radioactive Effluent Monitoring Instrumentation Surveillance 1
Requirements 15.7.4-1 15.7.5 Radioactive Effluent Release and Explosive Gas Concentration Limits 15.7 5-1 15.7.6 Radioactive Effluent Sampling and Analysis Requirements 15.7.6-1 15.7.7 Operational Environmental Monitoring Program 15.7.7-1 i
15.7.8 Administrative Controls 15.7.8-1 l
1 i
15-il l
Unit 1 - Amendment No. 82,86, 97,184 Unit 2 - Amendment No. 86,89,494,188
r 15.3.9 Emuent Release Radioactive Effluent Release limits, emuent sampling, and emuent analyses requirements are contained in the Radiological Effluent and Materials Control and Accountability Program Manual.
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15.3.9-1 l
Unit 1 - Amendment No. 97,184
- Unit 2 - Amendment No. 404,188
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9 15.4.10 RADIOLOGICAL ENVIRONMENTAL MONITORING The Radiological Environmental Monitoring Program (REMP) sampling and analyses requirements are addressed in the Radiological Effluent and Materials Control and Accountability Program Manual. The requirement for the REMP is specified in Section 15.7.8.3.
l' 15.4.10-1 Unit 1 - Amendment 20, 97,184 Unit 2 - Amendment E5,404,188 L
15.6.5 REVIEW AND AUDIT (Continued) 15.6.5.1 Manmoer's Suoervisorv Staff (Continued) f.
Review violations of Technical Specifications, such reviews to include reports, evaluations and recommendations.
g.
Perform special reviews, investigations or prepare reports thereon as requested by the Chairman of the Off-Site Review Committee.
h.
Review the Facility Fire Protection Program at least once per 24 months to ensure the program meets established commitments and requirements, i.
Investigate, review, and report on all reportable events.
J.
Review every release of radioactive material to the environment resulting in doses in excess of the annusi dose objectives specified in 10 CFR 50, Appendix I or resulting in the special report specified by Section 15.7.8.4.D. Such review willinclude a summary of evaluation, recommendation and disposition of corrective action to prevent recurrence.
k.
Review all changes to the manuals described in 4
Section 15.7.8.3.
l 15.6.5.1.9 The Manager's Supervisory Staff shall have the following responsibility:
j a.
Serve as an advisory committee to the Manager, b.
Make recommendations to the Manager for proposals under items a. through d. above. In the event of disagreement between a majority of the Supervisory Staff and decisions by the Manager, the course of action will be determined by the manager and the disagreement recorded in the Staff minutes.
15.6.5-3 Unit 1 - Amendment No. 97,446,184 Unit 2 - Amendment No. 40+,46% 188 l '.
l
15.7 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (RETS)
RETS do not directly expand the responsibilities of the licensed operators of the Point Beach Nuclear Plant Units 1 and 2, and the material contained in this section of these Technical Specifications will not be the subject of SRO/RO licensing examinations.
15.7.1 DEFINITIONS The definitions for frequently used terminology in these RETS are stated below. These definitions are supplemental to those definitions provided in Section 15.1.
A.
Members of the Pubhc l
Members of the public include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
B.
Offsite Dose Calculation Manual (ODCM) l The Offsite Dose Calculation Manual contains the methodology for the determination of gaseous and liquid effluent monitoring alarm or trip setpoints, the methodology for determining compliance with release limits, and the methodology used in the calculation of offsite doses due to radioactive gaseous and liquid effluents.
l C.
Radioactive Waste Handlina 1.
Process. Control Program (PCP)
The Process Control Program contains the methodologies used to ensure that the processing and packaging of solid radioactive waste will be accomplished in such a way as to assute compliance with 10 CFR Parts 20, 61, and 71, and all other Federal and State regulations goveming the disposal of the radioactive waste.
l 2.
Solidification The conversion of liquid wastes into a form that meets shipping and burial ground requirements.
D.
Radiological Effluent and Materials Control and Account = hili +v Prourem The Radiological Effluent and Materials Control and Accountability Program (REMCAP) specUied by 15.7.8.3 shall ensure that all radioactive effluent (materials released via liquid and atmospheric pathways as well as solid materials) from the Point Beach Nuclear Plant are controlled and accounted for in a manner which complies with the applicable regulations and shall ensure that control and I
accountability for atmospheric and liquid releases are supplemented by environmental sampling and dose calculations. The four major components of the REMCAP are the ODCM, the PCP, the Radiological Environmental Monitoring Program (REMP), and the Radiological Effluent Control Program (RECP). Other supporting guidance, procedures, manuals, or programs may be included or referenced but may not be subject to the program controls specified in 15.7.8.6 and 15.7.8.7.
t Unit _1 - Amendment 97,184 15.7.1-1 Unit 2 - Amendment 494,188
15.7.2 SITE DESCRIPTION Figure.15.7.2-1 is a site map for'5e Point Beach Nuclear Plant Units 1 and 2. The site map l
]
shows the site boundary and points within the site boundary from which gaseous and liquid 4
effluents are released. Fence locations are approximate.
l i.
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15.7.2-1 Unit 1 - Amendment 97,184 Unit 2 - Amendment 4Gb 188 u-__-_______________.
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i Unit 1 - Amendment No. 97.184 Figure 15.7.2-1 Unit 2 - Amendment No. 701.188 15.7.2-2 l
I, 15.7.3 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS Operability requirements have been removed from the Technical Specifications and moved to the REMCAP Manual.
15.7.3-1 Unit 1 - Amendment No. 97, 422, 462,184 Unit 2 - Amendment No. 4M, 426, 466,188
l l
l 15.7.4 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Surveillance requirements have been removed from Technical Specifications and moved to the REMCAP Manual.
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l 15.7.4-1 Unit 1 - Amendment No. 97,184 Unit 2 - Amendment No. 40+,188
r f.
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15.7.5 RADIOACTIVE EFFLUENT RELEASE AND EXPLOSIVE GAS CONCENTRATION LIMITS l
Applicability Applies to the explosive gas concentration in the radioactive gas decay tanks. Radioactive efnuent release limits have been removed from Technical Specifications and placed in the -
REMCAP Manual.
Objective To ensure explosive gas concentrations do not exceed the limits of Specification 15.7.5.A.
Specifications A.
Explosive Gas Mixture The concentration of oxygen in the on-service gas decay tank shall be limited to less than or equal to 4% by volume.
1.
If the concentration of oxygen in the on-service gas decay tank is greater than 4% by volume, immediately suspend all additions of waste gases to the on-service gas decay tank.
2.
Reduce the oxygen concentration to less than 4% oxygen by volume as soon as possible. If the on-service gas decay tank is at or near capacity and the tank must be isolated to permit the required decay time to conform with release limits, it will not be possible to immediately reduce the oxygen l
concentration. In this case, the tank will be isolated and the oxygen concentration reduced as soon as the gas decay requirements are satisfed.
l l
l l
l.
15.7.5-1 Unit 1 - Amendment No. 97,444,184 Unit 2 - Amendment No. 40+,447,188
15.7.6 RADIOACTIVE EFFLUENT SAMPLING AND ANALYSIS REQUIREMENTS Sampling and analysis requirements removed from Technical Specifications and placed in the REMCAP Manual.
15.7.6-1 Unit 1 - Amendment No. 97,184 Unit 2 - Amendment No. 494,188
n 15.7.7 OPERATIONAL ENVIRONMENTAL MONITORING PROGRAM The description of the environmental monitoring program has been removed from Technical i
Specifications and placed in the REMCAP Manual.
l l
t 15.7.7-1 Unit 1 - Amendment No. 97,444,462,184 Unit 2 - Amendment No. 494,447,466,188
e.-
15.7.8 ADMINISTRATIVE CONTROLS 15.7.8.1 Duties of the Manaaer's Suoervisorv Staff The duties of the Manager's Supervisory Staff with respect to these radiological effluent technical specifications are listed in Specification 15.6.5.1.8 at items J. and k.
I 15.7.8.2 Audits 4
(
A.
An audit of the activities encompassed by the Radioactive Effluent and Materials Control and Accountability Program (REMCAP), [the Offsite Dose Calculation Manual (ODCM), the Radiological Emuent Control Program (RECP), the Radiological Environmental Monitoring Program (REMP), and the Process Control Program (PCP)] and its implementing procedures shall be performed utilizing either offsite licensee personnel or a consulting firm.
B.
The results of the audit above shall be transmitted to l
the Chief Nuclear Officer and the Chairman of the Offsite Review Committee.
15.7.8.3 Plant Ooeratina Procedures and Procierns The Radioactive Emuent and Materials Control and Accountability Program (REMCAP) shall be established, implemented, and maintained in accordance with the provisions of Technical Specification 15.6.8. REMCAP shall assure that radioactive emuent and waste material from PBNP I
complies with applicable Federal, State, and burial ground regulations while keeping all exposures to members of the public as low as reasonably achievable (ALARA). This program shall conform to and implement the requirements of PBNP GDC 70 and of 10 CFR 50.34a and 10 CFR 50.36a for the control of radioactive effluents while maintaining doses from these emuents ALARA, shall implement the requirements of 10 CFR 50.34a and General Design Criterion 60 of Appendix A to 10 CFR 50 to suitably control the release and the processing of waste materials, shall conform to the guidance of Appendix l to 10 CFR 50 and PBNP GDC 17 for the assessment of radioactivity in the environs of PBNP, and shall include remedial actions to be taken whenever the program limits are exceeded. REMCAP shall be implemented and maintained under the procedures and methodologies specified in the four (4) manuals / programs listed below and supported, as required, by other procedures. Emuent and environmental monitoring shall be addressed in the Quality Assurance Program.
15.7.8-1
. Unit 1 -' Amendment No. 462,4M,184 Unit 2 - Amendment No. 466,464,188
s.
Environmental Manual (EM)- In order to assure conformance with PBNP GDC 17 and with the guidance of Appendix I to 10 CFR 50, this manual shall contain the Radiological Environmental Monitoring Program (REMP) methodology, parameters, and administrative functions required for monitoring, sampling, analyzing, and reporting of radiation levels and radionuclides concentrations in the environment around PBNP. The REMP shall require an annual milk survey and shall require that radioanalyses be conducted by a laboratory participating in an Interlaboratory Comparison Program.
b.
Radiological Effluent Control Program Manual (RECM) - The RECM shall contain the Radiological Effluent Control Program j
(RECP) parameters and methodologies needed in order to assure conformance with 10 CFR 50.36a for the control of effluents and for maintaining doses to the public ALARA and for compliance with 10 CFR 20.1302. The following RECP items are contained in the RECM:
1) radioactive effluent monitoring instrumentation operability, with actions to be taken if operability requirements are not met, and surveillance requirements, 2) radioactive effluent sampling and analyses requirements; 3) limitations on the concentrations of radioactive materials in
{
liquid effluents to the unrestricted area to 10 times the J
concentration value in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402;.
4) determination of the cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with ODCM methodology and parameters at least every 31 days; 5) assurance that the appropriate portions of the liquid and l.
gaseous effluent treatment system are used whenever the l
projected doses in a period of 31 days would exceed 2 percent of the 10 CFR 50, Appendix I dose guidelines; 6) limitations to the release rate of radioactive effluent to the atmosphere in order to assure that the following dose rates would not be exceeded at or beyond the site boundary:
l a.
500 mremlyr., total body, from noble gases, b.
3000 mrem /yr., skin, from noble gases, c.
1500 mremlyr., any organ, from I-131,1-133, H-3, and all radioactive particulate with a half-life greater than 8 days; 7) limitations on the annual and quarterly doses to a member of the public at or beyond the site boundary from I-131, 1-133, H-3, and radioactive particulate with a half-life > 8 15.7.8-3 Unit 1 - Amendment No. -97,184 Unit 2 - Amendment No. 404,188
1 4
4,-
days in effluents released to the atmosphere which f
conform to 10 CFR 50, Appendix 1, dose guidelines, and I
8) administrative functions and reporting requirements.
i c.
Offsite Dose Calculation Manual (ODCM) - The ODCM shall specify that the annual doses from PBNP effluent shall conform to the limits of Appendix I to 10 CFR 50 and of 40 CFR 190, shall contain the parameters and methodology used to calculate the doses to members of the public from PBNP liquid and
)
atmospheric releases in order to demonstrate compliance with these dose limits, and shall contain the methodology to calculate setpoints to ensure that the effluent radionuclides concentrations in l
unrestricted areas do not exceed the limits specifed in the RECP.
d.
Process Control Program (PCP) - The PCP shall provide the methodologies for assuring that the processing and packaging of solid radioactive wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61 and 71, and all other applicable Federal and State regulations goveming the disposal of the radioactive waste.
L 15.7.8-3 Unit 1 - Amendment No. -97,184 Unit 2 - Amendment No. 4Gt,188
I 15.7.8.4 RETS Reoortina Requirements The following written reports shall be submitted to the Administrator, U.S.
Nuclear Regulatory Commission Region lli with a copy to the Director, Office of Inspection and Enforcement, USNRC, Washington, DC 20555 within the time periods specified.
A. Annual Monitorina Reoort A report covering the operation of PBNP for the previous twelve (12)
I month period, or fraction thereof, ending on December 31, shall be submitted by May 1 of each year containing:
i 1.
RECP information relative to the quantities of radioactive liquid and gaseous effluents and solid radioactive waste released from PBNP during the reporting period. The information shall be consistent with the objectives outlined in the ODCM and RECM as well asSection IV.B.1 of Appendix l to 10 CFR 50 and 10 CFR 50.36a.
2.
New and.". pent Fuel Recelots and Shioments a.
Number and type of new fuel assemblies received during j
the reporting period, if any.
b.
Number of spent fuel assemblies shipped off site during the reporting period,if any.
3.
REMP Summaries and results from the REMP for the reporting period.
The information shall be consistent with the objectives outlined in the EM and in Sections IV.B.2, IV. B.3, and IV.C of Appendix I to 10 CFR 50.
4.
Leak Testha of Sealed Sources Resuits of required leak tests performed on sealed sources if the tects reveal the presence of 0.005 microcuries or more of removable contamination.
l 5.
Meteorological Data l
Meteorological data shall be kept in file on site for review by the NRC upon request. The data available willinclude wind speed, wind direction, and atmospheric stability. The data will be in the form of strip charts or hour-by-hour averages stored in electronic form for each of the parameters.
15.7.8-4 Unit 1 - Amendment No. 97,499,462,184 Unit 2 - Amendment No. 494,438,466,188
6.
REMCAP Chanoes
'A description of changes to the REM. CAP, ODCM, EM, RECM or PCP which were implemented and became effective during the reporting period shall be submitted pursuant to Specification 15.7.8.7.
7.
Sr.acial Circumstances Reoorts a.
In accordance with note 7 to RECM Table 3-2, if the l
Waste Gas Holdup System Explosive Gas Monitor is out of service for greater than 14 days.
b.
In accordance with the EM, factors which render the LLDs l
unschievable.
c.
In accordance with the EM, failure of the analytica!
l laboratory to participate in an Interlaboratory Comparison Prograrn.
B.
. Measured Radioactivity Above fictification Levels if the confirmed level of radioactivity remains above the notification levels specified in the EM, e written report describing the circumstance shall be prepared and l
submitted within thirty days of the confirmation that a notification level was exceeded C.
Radioactive Liould Effluent Treatment L
If the radioactive liquid or gaseous ef!'luent treatment system is inoperable and liquid or gaseous e#luents are being discharged for 31 days without the treatment required to meet the release limits specified in the RECM, a special report shall be prepared and submitted to the Commission within thirty days which includes the following information:
1.
Identification of the inoperable equipment or subsystem and the reason for inoperability.
I 2.
Actions taken to restore the inoperable equipment to operable status.
3.
Summary description of actions taken to prevent a recurrence.
D.
Radmactive Effluent Releases l
If the quantity of radioactive material actually released in liquid or gaseous effluents during any calendar quarter exceeds twice the quarterfy limit as specified in the RECM, a special report shall be prepared and submitted to the Commission within thirty days of determination of the release quantity.
15.7.8-5 Unit 1 - Amendment No. 97,184 Unit 2 - Amendment No. 444,188
.15.7.8.5 Maior Chanoe to Radioactive Liauld. Gaseous and Solid Waste Treatment Systems Licensee initiated major changes to the radioactive waste treatment systems (liquid, gaseous, and solid) shall be reported to the U.S. Nuclear Regulatory Commission with the annual update to the FSAR for the period in which the major change was complete. The discussion of each change shall include:
A. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59; B. Information necessary to support the reason for the change; C. A description of the equipment, components and processes involved and the interfaces with other plant systems; D. An evaluation of the change, which shows how the predicted releases of radioactive materials in liquid effluents and gaseous effluents and/or quantity of solid waste will differ from those previously predicted in the license application and amendments thereto; E. An evaluation of the change, which shows the expected maximum exposures to an individual in the unrestricted area and to the general population that differ from those previously estimated in the license application r.M amendments thereto; F. An estimate of the exposure to plant operating personnel as a result of the change.
15.7.8.6 Record Retention Records of reviews performed for changes made to the REMCAP Manual and to the following REMCAP components; the EM, RECM, ODCM, and PCP; shall be kept for the duration of the operating licenses of Units 1 and 2 of the Point Beach Nuclear Plant.
15.7.8.7 Revisions A. Process Control Program Revisions to the PCP shall be documented and records of reviews performed for the revision shall be retained as required by 15.7.8.6. The documentation shall contain:
1.
Information sufficient to support the change together with the appropnate analyses or evaluations justifying the change (s), and 2.
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
15.7.8-6 Unit 1 - Amendment. 97,184
- Unit 2 - Amendment 40+,188
3.
Revisions shall become effective after review and acceptance by the Manager's Supervisory Staff and approval by the Manager -
PBNP.
B. Revisions to the EM, ODCM, RECM and REMCAP l
1.
Revisions to the EM, ODCM, RECM and REMCAP shall be documented and reviews performed of the revision shall be retained as required in 15.7.8.6. The documentation shall contain:
(
a.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the revision, and l
b.
A determination that the change will maintain the levels of radioactive effluent control required pursuant to 10 CFR 20.1302,10 CFR 50.36a, Appendix I to 10 CFR 50, and 40 CFR 190.
2.
Shall become effective after review and acceptance by the Manager's Supervisory Staff and the approval of the Manager-
- PBNP, 3.
Shall be submitted to the Commission in the form of a complete.
l legible copy of the entire manual either as part of, or concurrent with, the Annual Monitoring Report for the period of the report in j
which the revision was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed. Each copy shallindicate the date (e.g., month / year) the revision was implemented.
4.
In addition to items 1-3 above, all changes regarding explosive gas must be made via the 50.59 process.
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i 15.7.8-7 Unit 1 - Amendment No.184 Unit 2 - Amendment No.188
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