ML20086E617
| ML20086E617 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/05/1995 |
| From: | Hansen A NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20086E619 | List: |
| References | |
| NUDOCS 9507120131 | |
| Download: ML20086E617 (15) | |
Text
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- i UNITED STATES j
NUCLEAR REGULATORY COMMISSION.
W ASHINGTON, D.C. 2066Mm01
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 MENDMENT TO FACILITY OPERATING LICENSE Amendment No.162 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has fcund that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated January 24, 1995, as supplemented by letters dated February 24, April 25, May 24, and June 1, 1995, complies with the stand?rds 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.
9507120131 950705 PDR ADOCK 05000266 P
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- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No.
DPR-24 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendicas A and B, l
as revised through Amendment'No.162
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately upon issuance.
The l
Technical Specifications are to be implemented within 45 days from the l
date of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION ff Allen G. Hansen, Project Manager l
Project Directorate III-3 l
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of issuance:
July 5,1995 i
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+3 May lt UNITED STATES i
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l jj NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2056fr4001
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WISCONSIN ELECTRIC POWER COMPANY DOCKET N0. 50-301 POINTBEACHNUCLEkRPLANT.UNITNO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.166 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 January 24, 1995, as supplemented by letters dated February 24, April 25, May 24, and June 1, 1995, 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 9
- :c 1
i 2.
Accordingly, the license is 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 Soecifications l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.166, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the 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.
FOR THE NUCLEAR REGULATORY COMMISSION N
Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation r
Attachment:
Changes to the Technical Specifications Date of issuance: July 5,1995
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a ATTACHMENT TO LICENSE AMENDMENT NOS,162 AND 166 t
TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of cnange.
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REMOVE INSERT l
TS 15.6.5-6 TS 15.6.5-6 TS 15.6.5-8 TS 15.6.5-8 j
TS 15.7.3-7 TS 15.7.3-7 l
NOTES FOR TS TABLE 15.7.6-1 NOTES FOR TS TABLE 15.7.6-1 (no page number specified)
(no page number specified)
NOTES FOR TS TABLE 15.7.6-2 NOTES FOR TS TABLE 15.7.6-2 i
(no page number specified)
(no page number specified).
TS 15.7.7-1 through TS 15.7.7-1 through iS 15.7.7-3 (3 pages)
TS 15.7.7-3 (3 pages)
TS 15.7.8-1 TS 15.7.8-1 TS 16.1-3 TS 16.1-3 i
1 I
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15.6.5.2.7 (Continued) h)
Any indication of an unanticipated deficiency in some' aspect of design or operation of safety related structures, systems, or components.
1)
Reports and meeting minutes of the Manager's Supervisory Staff.
AUDITS 15.6.5.2.8 Audits of facility activities shall be performed under the cognizance of the OSRC. These audits shall encompass:
a)
The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions.
b)
The performance, training and qualifications of the licensed operating staff.
c)
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety.
d)
The results of audits by the quality assurance organization on the performance of activities required by the Quality Assurance Program to meet the criteria of Appendix B,10 CFR 50.
e)
Any other area of facility operation considered appropriate by the President.
AUTHORITY 15.6.5.2.9 The OSRC shall report to and advise the President on those areas of responsibility specified in Section 15.6.5.2.7 and 15.6.5.2.8.
15.6.5-6 Unit 1 - Amendment NoJ13,22J1rL14,162 Unit 2 - Amendment No.48,77,95,117,166
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15.6.5.3 Fire Protection Audits a)
An independent fire protection-and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
i b)
An inspection and audit of.the fire protection and loss prevention program shall be performed by an outside qualified fire consultant-at intervals no greater than 3 years.
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l 15.6.5-8 Unit 1 - Amendment NO A3r7t%94d44.162 Unit 2 - Amendment No A8r7h95riU,166 1
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primary system is being degassed (other than normal gas stripping of the letdown flow).
If the monitoring system is out of service for greater than 14 days, in addition to the above sampling, a report of the cause and corrective action for failure and repair of the gas monitor shall be included in the Annual Monitoring Report.
Note 8:
If the number of channels operable is fewer than the minimum required, effluent releases via this pathway may continue provided grab samples are collected twice per week s'nd analyzed in accordance with Table 15.7.6-1.
Note 9:
If the number of channels operable is fewer than the minimum required, effluent releases via this pathway may continue provided the flow is estimated or determined with auxiliary indication at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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l 15.7.3-7 Unit 1 - Amendment No.-97,162 Unit 2 - Amendment No.-10h166
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d NOTES FOR TABLE 15.7.6-1 1.
The principal gamma emitter for which the gamma isotopic LLD applies is Cs-137. Because gamma isotopic analyses are performed, the LLDs for all other gamma emitters ar.e inherently determined by the operating characteristics of the counting system. All identifiable gamma emitters will be reported in the Annual Monitoring Report.
2.
A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses each batch shall be isolated and mixed to assurs representative sampling.
3.
A continuous release is the discharge of liquid wastes of a non-dis-crete volume; e.g., from a volume of a system that has an input flow during the release.
4.
A continuous composite is one in which the method of sampiing employed results in a specimen that is representative of the liquids released.
5.
Identified entrained noble gases shall be reported as gaseous effluents.
Unit 1 - Amendment No.-SJyl62 Unit 2 - Amendment No.4')hl66
NOTES FOR TABLE 15.7.6-2
- 1. The principal gama emitters for which the LLD specification applies are Cs-137 in particulates and Xe-133 in gases. Because gamma isotopic analyses are performed, the LLDs for all other gamma emitters are inherently determined by the operating characteristics of the count',ng system. All identifiable gama emitters will be reported in the Annual Monitoring Report.
- 2. Tritium grab samples will be taken every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling cavity is flooded.
3.
The ratio of the sample flow rate to the release flow rate shall be known or estimated for the time period covered by each sampling l
interval.
l 4.
Tritium grab samples will be taken every seven days from the drumming area ventilation exhaust / spent fuel pool area whenever there is spent fuel ir the spent fuel pool.
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Unit 1 - Amendment No. 91,162 l
Unit 2 - Amendment No. -M17166
15.7.7 OPERATIONAL ENVIRONMENTAL MONITORING PROGRAM i
Aeolicability This section applies to operational environmental radioactivity monitoring and sampling.
Obiective' To verify that plant operations have no significant radiological effects on' the environment.
Specifications A.
Environmental Monitorina Proaram
- 1. Environmental monitoring samples shall be taken at locations specified in the PBNP Environmental Manual according to the sampling and collection frequencies given in Table 15.7.7-1.
- 2. Deviations from the required sampling schedule as specified in Table 15.7.7-1, are permitted if hazardous conditions, seasonal unavailability, automatic sampling equipment malfunctions, and other legitimate reasons make the sample unobtainable.
If the radiological environmental monitoring program is not being conducted as specified in Table 15.7.7-1, a description of the reasons for not conducting the program and the plans for preventing a recurrence will be submitted with the next Annual Monitoring Report.
3.
If milk or vegetation samples become unavailable from one or more of the sample locations specified in the PBNP Environmental Manual, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.
The specific locations from which samples were unavailable may then be deleted from the monitoring program. The cause of the unavailability of samples and replacement samples shall be i
15.7.7-1 Unit 1 - Amendment No. JEA,162 Unit 2 - Amendment No.-4M,166
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identified in the next Annual Monitoring Report.
Figures and tables in the Environmental Manual are to be revised reflecting the new sample locations.
B.
Detection Capabilities
- 1. Environmental samples shall be analyzed as specified in Table 15.7.7-2.
- 2. The required detection capabilities for environmental sample analyses are tabulated in terms of the iower limits of detection (LLDs).
3.
If circumstances render the stated LLDs in Table 15.7.7-2 unachievable, the contributing factors shall be identified and described in the next Annual Monitoring Report.
C.
Notification levels 1.
If a measured level of radioactivity in any environmental medium exceeds the notification level listed in Table 15.7.7-3, resampling and/or reanalysis for confirmation shall be completed within 30 days of the determination of the anomalous result.
If the confirmed measured level of radioactivity remains above the notification level, a written report shall be submitted to the NRC in accordance with Section 15.7.8.4.B within thirty days of the confirmation. This report is not required if the measured level of radioactivity was not the result of plant effluents.
2.
If more than one of the radionuclides listed in Table 15.7.7-3 are detected in any environmental medium, a weighted sum calculation shall be performed if the measured concentration of a detected radionuclide is greater than 25% of the notification levels. For those radionuclides with LLDs in excess of 25% of the notification level, a weighted sum calculation need only be performed if the reported value exceeds the LLD. The weighted sum is calculated as follows:
weighted concentration (1)
+
concentration (2)
+...
notification level (1) notification level (2) sum If the calculated weighted sum is equal to or greater than 1, resampling and/or reanalysis for confirmation shall be completed within 30 days of the determination of the anomalous result.
If 15.7.7-2 Unit 1 - Amendment No. 97.114,162 Unit 2 - Amendment No. 401,117,166
i c i the confirmed ' calculated weighted sum remains equal to or greater than f
C 1,. a written report shall be submitted. to' the NRC in accordance with Section 15.7.8.4.8 within thirty'(30) days of the confirmation. This-calculation requirement and report is not required if the measured' level of radioactivity was not the result of plant effluents.
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- 3. All detected radionuclides shall be reported in the Annual Monitoring Reports. Naturally occurring nuclides such as Be-7, K-40,~and the l
U-238 and Th-232 decay series radionuclides shall not be included in this requirement.
D.
Land Use Census
- 1. The milk sampling program shall be reviewed annually, including a visual verification of animals grazing in the vicinity of the site boundary, to ensure that sampling locations remain as conservative as practicable.
I E.
Interlaboratory Comparison proaram f
- l. The environmental sampling analyses shall be performed by a laboratory
)
participating in an Interlaboratory Comparison Program.
2.
If the analytical laboratory is not participating in the Inter-laboratory Comparison' Program, a description of the corrective actions to be taken-to preclude a recurrence shall'be submitted in the Annual l
Monitoring Report.
Basis The operational radiological environmental monitoring program as outlined in Table 15.7.7-1 provides sufficient sample types and locations to detect and to evaluate changes in environmental radioactivity. Although radioactivity in plant effluents is continuously monitored and releases are well below levels which are f
considered safe upper limits, radiological environmental monitoring is a conservative measure undertaken to determine whether the operation of the Point Beach Nuclear Plant produces any significant radiological change in the I
surrounding environment.
{
Radioactivity is released.in liquid and gaseous effluents. Air particulate-samples and thermoluminescent dosimeters placed at various locations provide
- means of detecting changes in environmental radioactivity as a result of plant releases to the atmosphere.
15.7.7-3 Unit 1 - Amendment No.-97,162 Unit 2 - Amendment No. -leh166 1
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15.7.8 ADMINISTRATIVE CONTROLS 15.7.8.1 Duties of the Manaaer's Supervisory Staff The duties of the Manager's Supervisory Staff with respect to these radf clogical effluent technical specifications are listed in Specification 15.6.5.1.8 at Items j. and k.
15.7.8.2 Audits A.
An audit of the activities encompassed by the Offsite Dose Calculation Manual 'and the Process Control Program and its-implementing procedures shall be performed utilizing either offsite licensee personnel or a consulting firm.
B.
An audit of the radiological environmental monitoring program and the results thereof shall be performed utilizing either offsite licensee personnel or a qualified consulting firm.
C.
The results of the audits in A and B above shall be transmitted i
to the Vice-President - Nuclear Power and the Chairman of the Offsite Review Committee.
l 15.7.8.3 Plant Operatina Procedures The ODCM and the PCP shall be established and maintained in i
accordance with the provisions of specification 15.6.8.
Effluent and environmental monitoring shall be addressed in the Quality Assurance Program.
15.7.8.4 RETS Reportina Reauirements The following written reports shall be submitted to the Administra-tor, U.S. Nuclear Regulatory Commission Region III with a copy to the Director, Office of Inspection and Enforcement, USNRC, Washington, l
D.C. 20555 within the time periods specified.
1 A.
Annual Monitorina Report j
A report covering the operation of PBNP for the previous twelve (12) month period, or fraction thereof, ending on December 31, shall be submitted by May 1 of each year containing:
1.
Information relative to the quantities of liquid, gaseous and solid radioactive effluents released from the facility, and effluent volumes used in maintaining the releases 1
15.7.8-1 Unit 1 - Amendment No. 47dMr162 Unit 2 - Amendment No. MidB,166 I
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i 16.5 '6sportino Reauirements Specification 1.
As part of the Annual Monitoring Report, described in Section 15.7.8.4. A of Appendix A, the following shall be reported:
a.
All scheduled and unscheduled chemical discharge to the condenser cooling water.
i b.
A description of circulating water system operation for each unit which includes ambient temperature, intake temperature, discharge temperature, and circulating water system flow.
t 16.1-3 Unit 1 - Amendment No. -26r69r409,162 Unit 2 - Amendment No. -31774d4h166 i