ML20205D754
| ML20205D754 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/03/1985 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205B020 | List: |
| References | |
| NUDOCS 8510170083 | |
| Download: ML20205D754 (56) | |
Text
UNITED STATES
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E" NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. DPR-24 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated December 20, 1984 and supplemented April 12, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
8510170083 851003 PDR ADOCK 05000266 P
o 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-24 is hereby amended to read as follows:
8.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 97, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 3, 1985 l-
sgua Et%q'o t
d UNITED STATES 8'
~g NUCLEAR REGULATORY COMMISSION o
74 E
WASHINGTON, D. C. 20555
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WISCONSIN ELECTRIC POWER COMPANY 1
DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.101 License No. DPR-27
]
1.
The Nuclear Regulatory Comission (the Comission) has found that:
i A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated December 20, 1984 and supplemented April 12, Energy Act of 1954, as amended (the Act)quirements of the Atomic 1985, complies with the standards and re, and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission;
^
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health 1
and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; 1
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l 1
1
. 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 Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 101, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 20 days the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION L/.
Edward J.
utcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 3, 1985
ATTACHMENT TO LICENSE AMENDMENTS NO. 97 AND 101 TO FACILITY OPERATING LICENSE NO. DPR-24 AND DPR-27 DOCKET N05. 50-266 AND 50-301 Revise Appendix A as follows:
Remove Pages Insert Pages 15-11 15-11 15.3.9-1 15.3.9-1 15.3.9-2 15.3.9-2a 15.3.9-3 15.3.9-4 Table 15.4.1-1 (pg 2 of 4)
Table 15.4.1-1 (pg 2 of 4) 4 15.4.10-1 15.4.10-1 15.4.10-2 Table 15.4.10-1 Page 1 of 2 Table 15.4.10-1 Page 2 of 2 15.6.5-3 15.6.5-3 15.6.9-4 15.6.9-4 15.6.9-8 15.6.9-5 15.6.9-9 15.6.9-10 15.6.9-11 15.6.10-2 15.6.10-2 15.7.1-1 thru 15.7.1-3 15.7.2-1 SITE MAP FIGURE 15.7.1-1 15.7.3-1 thru 15.7.3-7 15.7.4-1 Table 15.7.4-1 Table 15.7.4-2 Table 15.7.4-2(continued)
Notations for Tables 15.7.4-1 and 15.7.4-2 15.7.5-1 thru 15.7.5-8 15.7.6-1 Table 15.7.6-1 Notes for Table 15.7.6-1 Table 15.7.6-2 Notes for Table 15.7.6-2 15.7.7-1 thru 15.7.7-4 Table 15.7.7-1 Table 15.7.7-1(continued)
Table 15.7.7-2 Notes for Table 15.7.7-2 Table 15.7.7-3 15.7.8-1 thru 15.7.8-6
O 8
TABLE OF CONTENTS (Continued)
Section Title Page 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 Adrainistrative 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 2
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 15.7 Radiological Effluent Technical Specifications (RETS) 15.7.1 Definitions 15.7.1-1 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 i
Surveillance Requirements 15.7.4-1 15.7.5 Radioactive Effluent Release Limits 15.7.5-1 15.7.6 Radioactive Effluent Sampling and Analysis j
Requirements 15.7.6-1 i
15.7.7 Operational Environmental Monitoring Program 15.7.7-1 15.7.8 Administrative Controls 15.7.8-1 i
k i
i Onit 1 Anendment No. 32, 1,97 15-11 Unit 2 - Amendnent No. 35,
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1 15.3.9 Effluent Release Radioactive Effluent Release limits are contained in specification 15.7.5.
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i Unit 1 - Amendment No.97 15.3.9-1 Unit 2 - Amendment No.101 1
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15.4.10 OPERATIONAL ENVIRONMENTAL MONITORING Radioactive ef fluent sampling and analysis requirements and opera-tional environmental monitoring requirements are specified in 15.7.6 and 15.7.7 respectively.
i Unit 1 - Amendment No. 29, 97 15.4.1& 1 Unit 2 - Amendment No. 25.101 m -
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TABLE 15.4.1-1 (Continued) gg (Page 2 of 4)
Channel l
77 Description Check Calibrate Test Remarks
{ { 10. Rod Position Bank Counters S (1)**
N.A.
N.A.
- 1) With analog rod position E $. 11. Steam Generator Level S **
R M (1)**
- 1) Includes test of logic for 55 AA reactor trip on low-low gg level and automatic actuation logic for auxiliary feedwater pumps yy 12. Steam Generator Flow Mismatch S **
R M **
gg 13. Charging Flow N.A.
R N.A.
- * ' 14. Residual Heat Removal Pump IM Flow-N.A.
R N.A.
g 15. Boric Acid Tank Level D
R N.A.
~
- 16. Refueling Water Storage Tank Level N.A.
R N.A.
- 17. Volume Control Tank Level N.A.
R N.A.
- 18. Reactor Containment Pressure D
R B/W(1)**
- 1) Isolation valve signal l
- 19. Radiation Monitoring System D
R M
- 1) Radioactive Effluent Monitor-i ing Instrumentation Surveil-lance Requirements are speci-i 3
fied in 15.7.4.
- 20. Boric Acid Control N.A.
R N.A.
I
- 21. Containment Water Level M
R N.A.
4
- 22. Turbine Overspeed Trip
- N.A.
R M (1)**
- 1) Block trip
- 23. Accumulator Level and Pressure S
R N.A.
- 0verspeed Trip Mechanism, and Independent Turbine Speed Detection and Valve Trip System.
- Not required during periods of refueling shutdown, but must be performed prior to starting up if it has not been performed during the previous surveillance period.
o 15.6.5 REVIEW AND AUDIT (Continued) 15.6.5.1 Manager's Supervisory Staff (Continued) h.
Review the Facility Fire Protection Program and implementing procedures at least once per 24 months, i.
Investigate, review, and report on all reportable events.
J.
Review every release of radioactive material to the environment in excess of the limits specified in Section 15.7.5.
Such review will include a sumary of evaluation, recommendation and disposition of corrective action to prevent recurrence.
k.
Review all changes to the PCP and ODCM.
15.6.5.1.7 The Manager's Supervisory Staff shall have the following responsibility:
a.
Serve as an advisory committee to the Manager.
b.
Make recomendations to the Manager for pro-posals 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.
c.
Make recomendations as to whether or not proposals considered by the Staff involve unreviewed safety questions.
d.
Review and approve the contents of a report for each reportable event. Copies of all such reports shall be submitted to the Vice Presi-dent - Nuclear Power and the Chairman of the Off-Site Review Comittee.
e.
Written minutes of each meeting shall be re-viewed by staff members and copies shall be pro-vided to the Vice President. Nuclear Power and Chaiman of the Off-Site Review Comittee.
15.6.5-3 Unit 1 - Amendment No. A3,85,9J. 97 Unit 2 - Amendment No. AB,89,95,101 l
15.6.9.2 DELETED 15.6.9.3 Unique Reporting Requirements The following written reports shall be submitted to the Director, Office of Nuclear Reactor Regulation, USNRC:
A.
Each integrated leak test shall be the subject of a summary technical report, including results of the local leak rate tests and isolation valve leak rate tests since the last report. The report shall include analysis and interpreta-tions of the results which demonstrate comp?iance with specified leak rate limits.
B.
Poison Assembly Removal From Spent Fuel Storage Racks l
Plans for removal of any poison assemblies from the spent fuel storage racks shall be reported and described at least 14 days prior to the planned activity.
Such report shall describe neutron attenuation testing for any replacement poison assemblies, if applicable, to confirm the presence of boron material.
C.
Overpressure Mitigating System Operation l
In the event the overpressure mitigating system is operated to relieve a pressure transient which, by licensee's evalua-tion, could have resulted in an overpressurization incident had the system not been operable, a special report shall be prepared and submitted to the Comission within 30 days. The report shall describe the circumstances initiating the transient, the effect of the system on the transient and any corrective action necessary to prevent recurrence.
15.6.9-4 Unit 1 - Amendment No. 79,85,97 Unit 2 - Amendment No. 63,89,101
D.
Dose Equivalent I-131 4
j With total cumulative operating time at a primary coolant specific activity greater than 1.0 microcurie per gram Dose Equivalent I-131 exceeding 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in any consecutive 6-month period, submit a report within 30 days indicating the number of hours above this limit.
E.
Failure of Containment High-Range Radiation Monitor I
A minimum of two in-containment radiation-level monitors with 8
7 a maximum range of 10 rad /hr (10 /hr for photos only) should be operable at all times except for cold shutdown and refueling outages.
"This is.specified in Table 15.3.5-5, item 7.
If the minimum number of operable channels are not restored to oper-able condition within seven days after failure, a special re-port shall be submitted to the NRC within thirty days following the event outlining the action taken, the cause of the inopera-bility and the plans and schedule for restoring the system to operable status.
F.
Failure of Main Steam Line Radiation Monitors l
If a main steam line radiation monitor (SA-11) fails and cannot be restored to operability in seven days, prepare a special report outlining the action taken, the cause of the inopera-bility and the plans and schedule for restoring the channel to operable status within thirty days of the event.
Unit 1 - Amendment No. 7J,92,97 I
,5-6.9-5 Unit 2 - Amentment No. 76,96,101 l
l I
..= - -.
M.
Test results, in units of microcuries, for leak tests performed pursuant to Specification 15.4.12.
N.
Record of annual physical inventory verifying accountability of sources subject to Specification 15.4.12.
O.
- Records of training and qualification for current plant NRC licensed staff and key personnel.
P.
- Records of in-service inspections performed pursuant to these Technical Specifications.
Q.
- Records of Quality Assurance activities required by the QA Manual.
s R.
- Records of reviews performed pursuant to 10 CFR 50.59.
S.
- Records of meetings of the Manager's Supervisory Staff and the Off-Site Review Comittee.
t l
T.
- Records of Environmental Qualification which are covered under the provisions of paragraph 15.6.12.
U.
- Records of the service life of all snubbers in accordance with Specifica-tion 15.4.13.4.
i V.
- Records of analyses for radiological environmental monitoring.
l l
- Items will be permanently retained.
{
i l
15.6.10-2 Unit 1 - Amendment No. 59,97 j
Unit 2 - Amendment No. 6A,101
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 SR0/R0 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.
Equivalent Curie An equivalent Curie is that quantity of a reference isotope that will produce the same dose as the actual amount of a particular isotope in question.
B.
Lower Level of Detection (LLD)
The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a real signal. For a particular measurement system, which may include radiochemical separation:
LLD =
4.66 Sb 6
E x V x 2.22 x 10 x Y x erp (-Aat)
Where:
i LLD = the a priori lower limit of detection as defined above, in micro-curies per unit volume or mass as applicable.
Sb = the standard deviation of the background counting rate or the counting rate of a blank sample as appropriate in counts per minute, E
= the counting efficiency in counts per disintegration, i
15.7.1-1 Unit 1 - Amendment No. 97 Unit 2 - Amendment No.101 i
o V
= the sample size in units of volume or mass as applicable, 2.22 x 108 = the number of disintegrations per minute per microcurie, Y
= the fractional radiochemical yield, when applicable, A
= the radioactivity decay constant for the particular radionuclide, and at = for plant effluents, at is the elapsed time between the midpoint of sample collection and time of counting: for environmental samples, at is the elapsed time between sample collection, or end of the collection period, and the time of counting.
Typical values of E, V, Y, and at will be used in the calculation. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
C.
Members of the Public Members of the public include all persons who are not occupationally 1
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 por-tions of the site for recreational, occupational, or other purposes not associated with the plant.
D.
Offsite Dose Calculation Manual (ODCM)
The Offsite Dose Calculation Manual contains the methodology for the determination of gaseous and liquid effluent monitoring alars 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.
E.
Radioactive Waste Handling 1.
The Process Control Program contains the methodologies used to ensure t
15.7.1-2 Unit 1 - Amendment No. 97 Unit 2 - Amendment No. 101 l
O that the processing and packaging of solid radioactive waste vill be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, and all other Federal and State regulations governing the disposal of the radioactive vaste.
2.
Solidification The conversion of liquid wastes into a form that meets shipping and burial ground requirements.
F.
Source Check A source check is an assessment of channel response when the channel detector is exposed to a source of increased radiation.
G.
Unrestricted Area An unrestricted area is any area at or beyond the site boundary where access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.
H.
Caseous Radioactive Effluent Treatment System The gaseous radioactive effluent treatment system consists of those components or devices utilized to reduce gaseous radioactive material in effluents. The system consists of the folleving:
a.
gas decay tanks, b.
drumming area ventilation exhaust duct filter assembly, c.
Unit 1 and 2 containment purge exhaust filter assemblies, d.
air ejector decay duct filter assembly, e.
auxiliary building ventilation filter assembly (nominal 11.214 cfm exhaust pathway),
f.
chemistry laboratory exhaust duct filter assembly, g.
service building ventilation exhaust duct filter assembly, h.
auxiliary building ventilation filter assemblies (nominal 34,150 cfm exhaust pathway)
I.
Liquid Radioactive Effluent Treatment System The liquid radioactive effluent treatment system consists of those components or devices utilized to reduce liquid radioactive material in effluents. The system consists of the following:
a.
blowdown evaporator or waste evaporator, i
b.
polishing demineralizers, l
c.
boric acid evaporator feed domineralizers, I
d.
boric acid evaporators, e.
boric acid evaporator condensate domineralizers.
Unit 1 - Amendment No. 97 1
15.7.1-3 Unit 2 - Amendment No.101 l
l y-
15.7.3 RADIOACTIVE EFTLLINT MONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS Applicability Applies to the operability and alarm or trip setpoint requirements for liquid and gaseous effluent monitoring instrumentation.
Objective To ensure liquid and gaseous radioactive effluents are adequately monitored and to ensure that alarm or trip setpoints are established such that effluent releases do not exceed the limits specified in Specification 15.7.5.
Specifications A.
Radioactive Liquid Effluent Monitoring Instrumentation
'i 1.
'The radioactive liquid effluent monitoring instrumentation channels
]
listed in Table 15.7.3-1 shall be operable. The alarm or trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
2.
If fewer than the minimum number of radioactive liquid effluent i
monitoring channels are operable, the action statement listed in Table 15.7.3-1 opposite the channel shall be taken. Best effort j
shall be made to return an inoperable channel to operable status within 30 days.
If the channel is not returned to an operable status within 30 days, the circumstances of the instrument failure and schedule for repair shall be reported to the NRC Resident Inspec-tor.
3.
If a radioactive liquid effluent monitoring instrumentation channel alarm or trip setpoint is found less conservative than required by the ODCM, the channel shall be declared inoperable or the setpoint j
shall be changed to the ODCM value or a more conservative value.
l B.
Radioactive Gaseous Effluent Monitorina Instrumentation l'
3.
The radioactive gaseous effluent monitoring instrumentation channels listed in Table 15.7.3-2 shall be operable. The alarm or trip setpoints 15.7.3-1 Unit 1 - Amendment No. 97 Unit 2 - Amendment No.101 L
~
.. _ _ _ _. _ _ _ ~
i of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
2.
If fewer than the minimum number of radioactive gaseous effluent monitoring channels are operable, the action statement listed in Table 15.7.3-2 opposite the channel shall be taken. Best effort shall be made to return an inoperable channel to operable status within 30 days.
If the channel is not returned to an operable status within 30 days, the circumstances of the instrument fail-ure and schedule for repair shall be reported to the NRC Resident Inspector.
3.
If the radioactive gaseous effluent monitoring instrumentation channel alarm or trip setpoint is found less conservative than required by the ODCM, the channel shall be declared inoperable or the setpoint shall be changed to the ODCM determined value or a i
more conservative value.
Unit 1 - Amendment No. 97 15.7.3-2 Unit 2 - Amendment No.101
___,u-
6 TABLE 15.7.3-1 j
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Operable Action 1.
Liquid Radwaste System a.
RE-223, Waste Distillate Tank Discharge, 1
Note 1 or RE-229, Service Water Discharge (for applicable unit) b.
RE-218, Waste Condensate Tank Discharge, 1
Note 1 or RE-229, Service Water Discharge (for applicable unit) c.
Waste Condensate Tank Discharge Flow 1
Note 4 Meter d.
Waste Distillate Tank Flow Rate Recorder 1
Note 4 2.
Steam Generator Blowdown System a.
For Each Unit; RE-219, Steam Generator 1
Note 2 Blowdown Liquid Discharge, or RE-22,2, Blowdown Tank Monitor, or RE-229, Service Water Discharge b.
Steam Generator Blowdown Flow Indicators 1
Note 9 (1 per steam generator) 3.
Service Water System a.
RE-229, Service Water Discharge 1
Note 3 (1 per unit) b.
For Each Unit; RE-216, Containment Cooling 1 Note 3 Fan Service Water Return, or RE-229, Ser-vice Water Discharge c.
RE-220, Spent Fuel Pool Heat Exchanger 1
Note 3 Service Water Outlet or RE-229, Service Water Discharge (for applicable unit) 4.
Retention Pond Discharge System a.
RE-230, Retention Pond Discharge 1
Note 3 b.
Retention Pond Discharge Composite 1
Note 8 Sampler c.
Retention Pond Discharge Flow Determination NA j
j Retention p ee discharge flow may be determined from pump run time and pump per-l formance curves.
Unit 1 - Amendment No.97 I
15.7.3-3 Unit 2 - Amendment No.101
i TABLE 15.7.3-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Operable Action Instrument 1.
Gas Decay Tank System 1
Note 1 RE-214, Noble Gas (Auxiliary a.
Building Vent Stack), or RE-315 Noble Gas (Auxiliary Building Vent SPING) 1 Note 4 b.
. Gas Decay Tank Flow Measuring Heter 2.
Auxiliary Building Ventilation System 1
Note 6 RE-214, Noble Gas (Auxiliary a.
Building Vent Stack) or RE-315, Noble Gas (Auxiliary Building Vent SPING) b.
Isokinetic Iodine and Particulate -
1 Note 5 Continuous Air Sampling System 3.
Condenser Air Ejector System RE-225, Noble Gas (Combined Air 1
Note 6 a.
Ejector Discharge Monitor); or RE-215, Noble gas (Air Eiector Monitors - 1 per unit); or RE-214, Noble Gas (Auxiliary Building Vent Stack); or RE-315, Noble Gas (Auxiliary Building Vent SPING) b.
Flow Rate Monitor - Air Ejectors 1
Note 9 4.
Containment Purge and Forced Vent System 1
Note 6 a.
RE-212, Noble Gas Monitors (1 per unit); or RE-305, Noble Gas (Purge Exhaust SPING - 1 per unit) b.
30 cfm Forced Vent Path Flow Indicators 1
Note 9 Unit 1 - Amendment No. 97 15.7.3-4 Unit 2 - Amendment No.101 i
o 1
TABLE 15.7.3-2 (CONTINUED)
Minimum o
Channels Operable Action Instrument c.
Iodine and Particulate -
Note 5 1
Continuous Air Samplers 1
Note 9 d.
Sampler Flow Rate Measuring Device 5.
Fuel Storage and Drumming Area Ventilation System RE-221, Noble Gas (Drumming Area a.
Stack), or RE-325, Noble Gas Note 6 1
(Drumming Area SPING) b.
Isokinetic Iodine and Particulate -
1 Note 5 Continuous Air Sampling System 6.
Gas Stripper Building Ventilation RE-224, Noble Gas (Gas Stripper a.
Building), or RE-305, (Unit 2 Note 6 1
Purge Exhaust SPING) b.
Iodine and Particulate -
Note 5 1
Continuous Air Sampler 1
Note 9 1
Sampler Flow Rate Measuring Device c.
7.
Waste Gas Holdup System Explosive Gas Monitcring System 1
Note 7 Oxygen Monitor
- a.
?
k i
- Effective upon completion of installation and checkout but in no case later than April 1,1986.
Unit 1 - Amendment No. 97 15.7.3-5 Unit 2 - Amendment No.101 l
l
NOTATIONS FOR TABLES 15.7.3-1 AND 15.7.3-2 e
Note 1:
If the number of channels operable is fewer than the minimum re-quired, effluent releases via this pathway may continue provided that prior to initiating a release, two separate samples are analyzed by two technically qualified people in accordance with the applicable I
part of Tables 15.7.6-1 and 15.7.6-2 and the release rate is reviewed by two technically qualified people.
Note 2:
If the number of channels operable is fewer than the minimum re-quired, effluent releases via this pathway may continue provided grab samples are analyzed for gamma radioactivity in accordance with Table 15.7.6-1 at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the secondary coolant specific activity is less than 0.01 pei/cc dose equivalent I-131 or once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the activity is greater than 0.01 pCi/cc dose equivalent I-131.
Note 3:
If the number of channels operable is fewer than the minimum re-quired, effluent releases via this pathway may continue provided that at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab samples are collected and analyzed in accordance with Table 15.7.6-1.
Note 4:
If the number of channels operable is fewer than the minimum re-quired, effluent releases via this pathway may continue provided the flow rate is estimated at least once every four hours during actual gaseous or liquid batch releases.
Note 5:
If the number of channels operable is fewer than the minimum re-quired, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment.
Note 6:
If the number of channels operable is fewer than the minimum re-quired, effluent releases via this pathway may continue provided grab samples are collected at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and are analyzed in accordance with Table 15.7.6-2.
Note 7:
If the number of channels operable is fewer than the minimum re-quired, addition of waste gas to the Waste Gas Boldup System may continue for up to 14 days, provided grab samples are taken from the on-service gas decay tank and analyzed either daily during normal operations or every four hours when the Unit 1 - Amendment No. 97 15.7.3-6 Unit 2 - Amendment No.101 1
l 1
primary system is being degassed (other than normal gas stripping of um 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 Semiannual Monitoring Report.
Note 8:
If the number of channels operable is fewer than the minimum re-quired, effluent releases via this pathway may continue provided grab samples are collected twice per week and analyzed in accordance with Table 15.7.6-1.
Note 9:
If the number of channels operable is fewer than the minimum re-quired, 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 />.
l L
Unit 1 - Amendment No. 97 15.7.3-7 Unit 2 - Amendment No.101
15.7.4 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION SURV l
Applicability Applies to the periodic inspection, testing, calibration and verification of operability requirements for radioactive liquid and gaseous effluent a
monitoring instrumentation.
Objective i
To verify that radioactive liquid and gaseous effluent monitoring instru-mentation are periodically demonstrated to be operable.
j Specifications Radioactive Liquid Monitorina Instrumentation Surveillance Requirements A.
Each radioactive liquid effluent monitoring instrumentation channel 1.
shall be demonstrated operable by performance of the channel check, calibration, functional test, and source check at the frequencies shown in Table 15.7.4-1.
Radioactive Gaseous Monitoring Instrumentation Surveillance Requirements B.
Each radioactive gaseous effluent monitoring instrumentation channel 1.
shall be demonstrated operable by performance of the channel check, calibration, functional test, and source check at the frequencies shown in Table 15.7.4-2.
Unit 1 - Amendment No. 97 15.7.4-1 Unit 2 - Amendment No. 101
TABLE 15.7.4-1
((
RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS eo Channel Functional Source m
Instrument Description Check Calibrate Test Check kk 1.
Liquid Radwaste System
- a. RE-223, Waste Distillate Tank Discharge D
R Q
P
.E5
- b. RE-218, Waste Condensate Tank Discharge D
R Q
P 22PP
- c. Waste Condensate Tank Discharge Flow Meter P/D R
NA NA p
- d. Waste Distillate Tank Flow Rate Recorder P/D R
NA NA 2.
Steam Generator Blowdown System
- a. RE-219, Steam Generator Blowdown Liquid Discharge (1 per unit)
D R
Q M
- b. RE-222, Blowdown Tank Monitor (1 per unit)
D R
Q M
- c. Steam Generator Blowdown Flow Indicator (1 per steam generator)
D R
NA NA 3.
Service Water System
- a. RE-229, Service Water Discharge (1 per unit)
D R
Q M
- b. RE-216, Containment Cooling Fan Service Water Return (1 per unit)
D R
Q M
- c. RE-220, Spent Fuel Pool Heat Exchanger Service Water Outlet D
R Q
M 4.
Retention Pond Discharge System
- a. RE-230, Retention Pond Discharge D
R Q
M
- b. Retention Pond Discharge Composite Sampler W
NA NA NA i
- c. Retention Pond Discharge Effluent Sump Pumps W
R NA NA
TABLE 15.7.4-2 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ae Channel Functional Source N'
Check Calibrate Test Check Channel Description El
@g 1.
Gas Decay Tank System gg
- a. RE-214, Noble Gas (Auxiliary Building Vent D
R Q
M Stack) zz
??
- b. Gas Decay Tank Flow Measuring Device P
R NA NA we P
2.
Auxiliary Building Ventilation System i
- a. RE-214, Noble Gas (Auxiliary Building Vent D
R Q
M Stack)
- b. RE-315, Noble Gas (Auxiliary Building SPING)
D R
Q M
- c. Isokinetic Iodine and Particulate Continuous W
R NA NA Air Sampling System 3.
Condenser Air Ejector System l
- a. RE-225, Noble Gas (Combined Air Ejector D
R Q
M Discharge)
- b. RE-215, Noble Gas (Air Ejectors - 1 per unit)
D R
Q M
- c. Flow Rate Monitor - Air Ejectors D
R NA NA (1 per unit) 4.
Containment Purge and continuous Vent System
- a. RE-212, Noble Gas (1 per unit)
D R
Q M*
- b. 30 cfm Vent Path Flow Indicator P/D R
NA NA 1
1
TABLE 15.7.4-2 (Continued)
EE Channel Functional Source Instrument Description Check Calibrate lest Check m _.,
- c. RE-305, Noble Gas (Purge Exhaust SPING -
kk 1 per unit)
D R
Q M*
wa
- d. Iodine and Particulate Continuous Air Sampler P/W NA NA NA
((
- e. Sampler Flow Rate Measuring Device P/D R
NA NA O O 5.
Fuel Storage and Drumming Area Ventilation Stack
- a. RE-221, Noble Gas (Drumming Area Vent Stack)
D R
Q M
- b. RE-325, Noble Gas (Drumming Area SPING)
D R
Q M
- c. Isokinetic Iodine and Particulate Continuous Air Sampling System W
NA NA NA 6.
Gas Stripper Building Ventilation System
- a. RE-224 Noble Gas D
R Q
M
- b. Iodine and Particulate Continuous Air Sampler W
NA NA NA
- c. Sampler Flow Rate Measuring Device W
R NA NA 7.
Waste Gas Holdup System Explosive Gas Monitoring System D
Q**
Q NA
- a. Oxygen Monitor *
- Effective upon completion of installation and checkout but in no case later than April 1,1986.
I
NOTATIONS FOR TABLES 15.7.4-1 AND 15.7.4-2 0 = Daily W = Weekly M = Monthly Q = Quarterly R = Each Refueling Interval (but not to exceed 18 months) i P/D = Prior to or immediately upon initiation of a release or daily if a release continues for more than one day P/W = Prior to or immediately upon initiation of a release or weekly if a release continues for more than one week P = Prior to or immediately upon initiation of a release
- = Source check required prior to containment purge
- = The channel calibration shall include the use of standard gas samples appropriate to the recommendations of the manufacturer of the gas analyzer equipment in use and include calibration points in the range of interest.
i l
l Unit 1 - Amendment No. 97 Unit 2 - Amendment No. 101
15.7.5 RADIOACTIVE EFFLUENT RELEASE LIMITS Applicability Applies to the controlled release of radioactive materials in liquid and gaseous effluents to unrestricted areas.
Objective To ensure controlled releases of radioactive materials in liquid and gaseous effluents to unrestricted areas are within concentration limits specified in 10 CFR 20 and to ensure the quantities of radioactive material released during any calendar year are such that resulting radiation exposures do not exceed limits corresponding to the 10 CFR 50 Appendix I dose objectives.
Specifications A.
Radioactive Liquid Effluent Concentrations 1.
Alarm setpoints for liquid effluent monitors shall be determined and adjusted utilizing the methodologies and parameters given in the ODCM.
2.
The liquid effluent monitor setpoints shall be established to ensure that radioactive materials released as effluents shall not result in concentrations to unrestricted areas in excess of the values specified in 10 CFR 20, Appendix B, Table II.
3.
During release of radioactive liquid effluents, at least one l
condenser circulating water pump shall be in operation and the service water return header shall be lined up only to the unit whose circulating water pump is operating.
i I
j B.
Radioactive Liquid Effluent Release Limits 1.
The annual calculated total quantity of radioactive material above background released from PBNP in liquid effluents shall not result in an unrestricted area estimated annual dose or dose commitment from all j
exposure pathways to any individual in excess of 6 millires to the total body or 20 millires to any crgan.
15.7.5-1 Unit 1 - Amendment No. 97 Unit 2 - Amendment No.101
s 2.
Quarterly limits are defined as one quarter (1/4) of the annual a
limits.
3.
Compliance with these release limits will be demonstrated by periodic calculations utilizing either of the following methods:
the calculation of doses based on actual releases; or a.
a b.
the calculation and comparison of equivalent Curies released to equivalent Curie release limits, which would result in the above described dose limits, as described in the ODCM.
The methodology for converting actual activity to equivalent activity is provided in the ODCM and is based upon dose con-version fcetors contained in Regulatory Guide 1.109, Revision 1, October 1977.
C.
Radioactive Gaseous Effluent Concentrations 1.
Alarm setpoints for the gaseous effluent monitors shall be determined and adjusted utilizing the methodologies and parameters given in the ODCM.
2.
The gaseous effluent monitor setpoints are established to ensure that radioactive materials released shall not re-sult in concentrations to unrestricted areas in excess of the values specified in 10 CFR 20, Appendix B, Table II.
3.
During the release of radioactive gaseous effluents from the gas decay tanks through the auxiliary building vent, at least one auxiliary building exhaust fan shall be in operation.
D.
Radioactive Gaseous Effluent Release Limits 1.
The annual calculated total quantity of radioactive materials above background released from PBNP to the atmosphere shall not result in an unrestricted area estimated annual dose or dose commitment from all exposure pathways to any individual in excess of the following:
10 milliram to the total body or 30 millires to the skin from l
a.
gaseous effluents near ground level; and I
i l
Unit 1 - Amendment No. 97 15.7.5-2 Unit 2 - Amendment No.101 O
g w
y
b.
30 millirem to any organ from all radiciodines and radioactive material in particulate form.
2.
Quarterly limits are defined as one quarter (1/4) of the annual limits.
3 Compliance with these release limits will be demonstrated by periodic calculations utilizing either of the following methods:
a.
the calculation of doses based on actual releases, or b.
the calculation and comparison of equivalent Curies released to the equivalent Curie release limits, which would result in the above dose limits, as described in the ODCM.
The methodology for converting actual activity to equivalent activity is provided in the ODCM and is based upon dose conversion factors con-tained in Regulatory Guide 1.109, Revision 1, October 1977.
E.
Tritium Adjustment The release limit for tritium in liquid effluents may be increased, provided it is accompanied by a proportional decrease in the release limit for tritium in gaseous effluents. Similarly, the release limit for tritium in gaseous effluents may be increased, provided it is accompanied by a propor-J tional decrease in the release limit for tritium in liquid effluents. The tritium adjustment will be made in accordance with the following formula:
Annual Liquid Tritium Releases Annual Gaseous Tritium Releases 1 2.0 Annual Liquid Tritium Limit Annual Gaseous Tritium Limit F.
Quarterly Summary 1.
A summary of radioactive effluent releases shall be made on a j
quarterly basis as described in the ODCM.
2.
If the calculations required by B.3 or D.3 of this specification exceed the corresponding quarterly limit during any calendar quarter, a summary of radioactive effluent releases shall be made monthly until it is determined that release quantities are within the annual limits.
3.
If the calculations required by B.3 or D.3 of this specification exceed twice the corresponding quarterly 1Leit during any calendar quarter, actual doses will be calculated as described in the ODCM, and a special report will be prepared and submitted per Specification 15.7.8.4.E.
Unit 1 - Amendment No. 97 15.7.5-3 l
Unit 2 - Amendment No.101 i
4.
If the calculations required by B.3 or D.3 of this specification a
demonstrate that quarterly releases exceed the quarterly limit, cor-rective actions shall be taken to ensure that subsequent releases in that calendar year will be in compliance with quarterly and annual limits.
e G.
Radioactive Effluent Treatment 1.
The gaseous radioactive ef fluent treatment system shall be operated.
If the gaseous effluent treatment system becomes inoperable, the effluent reporting requirements of section 15.7.5.F of this Specifi-cation shall apply. These provisions do not include the gas decay tanks, the auxiliary building ventilation exhaust charcoal filter, and the air ejector decay duct charcoal filter assembly, A gas decay tank ("s) shall be operated whenever required to main-a.
tain gaseous releases within the limits of Specification 15.7.5.D.
b.
The auxiliary building ventilation exhaust charcoal filter shall be operated when required to maintain gaseous releases within the limits of Specification 15.7.5.D for radiciodines.
The air ejector charcoal filter shall be operated when c.
required to maintain releases within the limit of Specifi-cation 15.7.5.D for radiciodines.
2.
The liquid radioactive effluent treatment system shall be operated.
If the liquid radioactive effluent system becomes inoperable, the effluent reporting requirements of section 15.7.5.F of this Specifi-I cation shall apply. These provisions do not include the processing of l
steam generator blowdown, the processing of liquid wastes collected in the vaste holdup tank, the processing of secondary side sampling and I
turbine building wastes through the retention pond, and the processing of preplanned tank batch releases.
Steam generator blowdown shall be processed to reduce radio-a.
active effluents when required to maintain releases within I
the limits of Specification 15.7.5.B.
b.
Wastes collected in the waste hol' dup tank shall be processed to reduce radioactive effluents when required to maintain l
releases within the limits of Specification 15.7.5.B.
Unit 1 - Amendment No. 97 15.7.5-4 Unit 2 - Amendment No. 101 o
y
Preplanned tank batch releases may be made without processing c.
under any of the following conditions, provided the release limits of Specification 15.7.5.B are not exceeded:
1.
Processing or disposal of tank contents would prevent plant operation or delay plant start-up or shutdown; or 2.
The tank release is necessary to conform to Technical Specification operating requirements; or 3.
The tank release is necessary to eliminate a chemical contaminant to satisfy chemistry specifications; or 4.
The tank release is desired for any other reason and a cost-benefit analysis has been performed.
H.
Total Dose 1.
Compliance with the provisions of Appendix I to 10 CFR 50 is adequate demonstration of conformance to the standards set forth in 40 CFR 190.
2.
If the calculations required by B.3 or D.3 of this specification exceed twice the annual limits as specified in Specifications 15.7.5.B.1 and 15.7.5.D.1, dose calculations shall be performed as described in the ODCM and shall include exposures from effluent path-ways and direct radiation contributions from the reactor units and from any outside storage tanks.
3.
A report will be submitted to the Commission within 30 days upon completion of the dose calculations regulred by Specifi-cation 15.7.5.H.2, if the calculated dose to any member of the general public exceeds the 40 CFR 190 annual dose limits.
I.
Explosive Gas Mixture The concentration of oxygen in the on-service gas decay tank shall i
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 Lunediately suspend all additions of waste gases to the on-service gas decay tank.
I i
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' l
l l
Unit 1 - Amendment No. 97 15.7.5-5 Unit 2 - Amendment No.101
near capacity and the tank must be isolated to permit the required decay time to conform with release limits of 15.7.5.D. it will not be In this case, possible to immediately reduce the oxygen concentration.
the tank will be isolated and the oxygen concentration reduced as soon as the gas decay requirements are satisfied.
a J.
Solid Radioactive Waste The solid radwaste system shall be used in accordance with the Process Control Program to process radioactive wastes to meet all shipping and burial ground requirements. If the provisions of the Process Control Program are not satisfied, shipments of defectively processed or defec-tively packaged radioactive vaste from the site will be suspended.
The Process Control Program shall be used to verify solidification of radwaste.
Basis Liquid wastes from the radioactive vaste disposal system are diluted by the circulating water system prior to release to Lake Michigan (
With two pumps the rated f 3cv of the circulating water system is approxi-operating per unit, mately 356,000 gpm per unit. Operation of a single circulating water pump per unit reduces the nominal flow rate by about 40%. Liquid waste from the vaste disposal system may be discharged to the circulating water system of either unit via the service water return header. Becauce of the low radioactivity levels in the circulating water discharge, the concentrations of liquid radioactive effluents at this point are not measured directly. The concentrations in the circulating water discharge are calculated from the measured concentration of the the discharge flow rate of the effluent and the nominal flow in liquid effluent, the circulating water system.
The concentration of liquid radioactive wastes in the circulating water discharge I
does not exceed 10 CFR 20 MPC values. The average concentrations at the intake of the nearest public water supply are well below the MPC values of 10 CFR 20, Appendix B( }.
Thus, discharge of liquid wastes'not exceeding the design release limits will not result in significant exposure to members of the public as a result of consumption of drinking water from the lake, even if the effect of potable water treatment systems on reducing radioactive concentrations of the water supply is conservatively neglected.
Unit 1 - Amendment No. 97 15.7.5-6 Unit 2 - Amendment No.101 i
Prior to release to the atmosphere, gaseous wastes are mixed in the auxiliary building vent with the flow from at least one of two auxiliary building exhaust s
fans. Further dilution then occurs in the atmosphere.
The limits prescribed in these Specifications take atmospheric dilution into account and ensure that at the point of maximum ground concentration (site boundary) the requirements of 10 CFR 20 will not be exceeded at any time and that the design objectives of Appendix I to 10 CFR 50 will not be exceeded on an annual basis. The limits and objectives are based on the high-est long term values of X/Q that occur at the nearest portion of the site boundary.
The release of radioactive materials in liquid effluents to unrestricted areas will not exceed the limits set forth in Section 15.7.5.B.1 and will be as low as is reasonably achievable in accordance with the requirements of 10 CFR Part 50.34a and 50.36a. These Specifications provide reasonable assurance that the resulting average annual dose or dose commitment from liquid effluents from each unit of tne Point Beach Nuclear Plant for any individual in an unrestricted area from all pathways of exposure will not exceed 3 mrem to the total body or 10 mrem These Specifications also provide reasonable assurance that no to any organ.
individual in an unrestricted area will receive an 4.nnual dose to the total body greater than 5 arem or an annual dose to the skin greater than 15 arem from these gaseous effluents.
At the same time, these Specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided with a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such numerical guides for design objectives but still within levels that assure that the average population exposure is equivalent to small fractions of doses from natural background radiation.
The release limits set forth in this Specification are derived from the dose In the evaluation performed in accordance with Appendix I to 10 CFR Part 50.
evaluation, certain maximum calculated dotes to an individual result from the calculated effluent releases. Release limits are defined by scaling calculated Unit 1 - Amendment No.97 Unit 2 - Amendment No.101 15.7.5-7
i releases upward to the point at which corresponding doses reach the applicable limit specified in Appendix I to 10 CFR Part 50.
a The radioactive liquid and gaseous effluent instrumentation is provided to monitor and control the releases of radioactive materials in liquid and gaseous effluents during actual or potential releases. The trip setpoints for these instruments are calculated utilizing the methodology in the Offsite Dose Cal-i culation Manual.
The requirement that the appropriate portions of the liquid and gaseous radwaste treatment systems be used when specified provides assurance that the releases of radioactive materials in liquid and gaseous effluents will be kept "as low as is reasonably achievable".
Compliance with the provisions of Appendix I to 10 CFR Part 50 constitutes adequate demonstration of conformance to the standards set forth in 40 CFR Part 190 regarding the dose connitment to individuals from the uranium fuel cycle. The Specifications require that if actual quantities of radioactive materials released exceed twice the quantities associated with the design dose objective of Appendix 1 to 10 CFR Part 50, actual doses will be calcu-lated and a special report will be submitted.
l
References:
(1) FSAR, Seccion 10.2 (2) FSAR, Section 2, Appendix 2A Unit 1 - Amendment No. 97 (3) FSAR, Sections 2.6 and 2.7 Unit 2 - Amendment No.101 15.,s. o, -8
15.7.6 RADIOACTIVE EFFLUENT SAMPLING AND ANALYSIS REQUIREMENTS e
Applicability Applies to the sampling frequency, analysis frequency, and analysis requirements for radioactive liquid and gaseous effluents.
a Objectives To verify that the concentrations and quantities of radioactive material released from the site in liquid and gaseous effluents do not exceed the limits specified in Specification 15.7.5.
Specifications A.
Radioactive Liquid Waste Sampling and Analysis 1.
The concentration of radioactivity in liquid waste shall be deter-mined by sampling and analysis in accordance with Table 15.7.6-1.
B.
Radioactive Gaseous Waste Sampling and Analysis 1.
The concentration of radioactivity in gaseous wastes shall be deter-mined by sampling and analyses in accordance with Table 15.7.6-2.
Unit 1 - Amendment No.97 15.7.6-1 Unit 2 - knendment No.101 l
O TABLE 15.7.6-1 EE p;
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM rw e e Lower Level gg 3
Sampling Minimum Type of of Detection me Liquid Release Type Frequency Analysis Frequency Activity Analysi
@Ci/cc) mo 2
- 1. Batch Releases
-7
- a. Waste Condensate Tank Prior to Prior to Release Canana Emitters 5 x 10-6 zz
??
- b. Waste Distillate Tank Release I-131 1 x 10 5$
- c. Monitor Tanks
,7
- d. Other tanks containing Monthly on composites ob-Gross Alpha 1 x 10
~
-5 radioactivity to be dis-tained from batches re-Tritium 1 x 10
- charged, leased during the current month
-8 Quarterly on composites Sr-89/90 5 x 10 obtained from batches re-leased during the current quarter 3
- 2. Continuous Releases 5x10((
- a. Steam Generator Blowdown Grab Samples Twice Weekly Gaauna Emitters Twice Weekly I-131 1 x 10
~
- b. Service Water Monthly on Grab Gross Alpha 1 x 10, Composites Tritium I x 10
-8 Quarterly on Grab Sr-89/90 5 x 10 Composites
- c. Retention Pond Continuous Weekly Gamma Emitters 5 x 10 Composite I-131 1x 10 4
Monthly on Weekly Gross Alpha 1x10[I Composite Tritium 1 x 10
-0 Quarterly on Sr-89/90 5 x 10 Monthly Composites.
e NOTES FOR TABLE 15.7.6-1
- 1. The principal gamma emitter for which the gamma isotopic LLD applies Because gamma isotopic analyses are performed, the LLDs is Cs-137.
i for all other gamma emitters are inherently determined by the operating All identifiable gamma characteristics of the counting system.
emitters will be reported in the Semiannual 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 assure 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 sampling employed results in a specimen that is representative of the liquids released.
- 5. Identified entrained noble gases shall be reported as gaseous effluents.
i l
l l
i Unit 1 - Amendment No.97 Unit 2 - Amendment No.101 l
l
TABLE 15.7.6-2 p
RADIOACTIVE GASEGUS WASTE SAMPLING AND ANALYSIS PROGRAM ru a e s Lower Level e$
Sampling Minimum Type of of Detection!
g2 E E Gaseous Release Type Frequency Analysis Frequency ~
Activity Analysis (pCi/cc) 55 55
_4 mz
- 1. Gas Decay Tank Prior to Prior to Release Gasuna Emitters 1 x 10 PP Release 1 x 106
- 2. Containment Purge or Prior to Purge Prior to PurRe Ganana Emitters 2
Continuous Vent or Vent or Vent Tritium 1 x 10-
- 3. Continuous Releases:
Continuous Weekly Analysis Gauuna Emitters 1 x 10'II 3
-12 of Charcoal and I-131 1 x 10
- a. Unit 1 Containment Vent Particulate Samples
- b. Unit 2 Containment Vent
~II
- c. Drumming Area Vent Monthly Composite Grosfi Alpha 1 x 10
- d. Gas Stripper Building Vent of Particulate Sample
- e. Auxiliary Building Vent
-II Quarterly Composite Sr-89/90 1 x 10 of Particulate Sample
-6 Noble Gas Monitor Noble gases 1 x 10 Gross Beta or gansna Monthly Monthly Gausna Emitters 1 x 10 (Grab)
-6 Monthly Tritium 1 x 10
e NOTES FOR TABLE 15.7.6-2
- 1. The principal gamma emitters for which the LLD specification applies are Cs-137 in particulates and Xe-133 in gases. Because gamma isotopic 8-analyses are performed, the LLDs for all other samma emitters are in-herently determined by the operating characteristics of the counting All identifiable gamma emitters will be reported in the Semi-system.
annual honitoring 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 interval.
- 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 in the spent fuel pool.
Unit 1 - Amendment No. 97 Unit 2 - Amendment No.101
15.7.7 OPERATIONAL ENVIRONMENTAL MONITORING PROGRAM e
Applicability This section applies to operational environmental radioactivity monitoring i
and sampling.
Objective To verify that plant operations have no significant radiological effects on the environment.
Specifications A.
Environmental Monitoring Program Environmental monitoring samples shall be taken at locations 1.
specified in the PBNP Environmental Manual according to the sampling and collection frequencies given in Table 15.7.7-1.
Deviations from the required sampling schedule as specified in 2.
Table 15.7.7-1, are permitted if hazardous conditions, seasonal unavailability, automatic sampling equipment malfunctions, and If the other legitimate reasons make the sample unobtainable.
radiological environmental monitoring program is not being con-ducted 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 Semiannual 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 I
30 days. The specific locations from which samples were unavail-The cause able may then be deleted from the monitoring program.
of the u'navailability of samples and replacement samples shall be Unit 1 - Amendment No. 97 15.7.7-1 Unit 2 - Amendment No. 101 l
l
id:ntified in the next Staiannual Monitoring Rsport. Figures and tables in the Environmental Manual are to be revised reflecting the new samole locations.
B.
Detection Capabilities 1.
Environmental samples shall be analyzed as specified in Table 15.7.7-2.
6 i
2.
The required detection capabilities for environmental sample 8
analyses are tabulated in terms of the lower limits of detection (LLDs).
3.
If circumstances render the stated LLDs in Table 15.7.7-2 unachiev-able, the contributing factors shall be identified and described in next Semiannual 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 anamolous result.
If the con-firmed measured level of radioactivity remains above the notifi-cation 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 calcula-tion shall be performed if the measured concentration of a detec-ted radionuclide is greater than 25% of the notification levels.
For those radionuclides with LLDs in excess of 25% of the notifi-cation level, a weighted sum calculation need only be performed if the reported value exceeds the LLD.
The weighted sua is calculated as follows:
,,,, _ weighted concentration (1) concentration (2) notification level-(1) notification level (2) sum If the calculated weighted sua is equal to or greater than 1, resampling and/or reanalysis for confirmation shall be completed within 30 days of the determination of the ananalous result. If Unit 1 - Amendment No.97 15.7.7-2 Unit 2 - Amendment No.101 l
l
the confirmed calculated weighted sum rcrains equal to or greater than 1, a written report shall be submitted to the NRC in accor-dance with Section 15.7.8.4.B within thirty (30) days of the con-firmation. This calculation requirement and report is not required if the measured level of radioactivity was not the result of plant effluents.
3.
All detected radionuclides shall be reported in the Semiannual n
Monitoring Reports. Naturally occurring nuclides such as Be-7, K-40, and the 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 con-servative as practicable.
E.
Interlaboratory Comparison Program l
1.
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 tbr Inter-laboratory Comparison Program, a description of the corrective actions to be taken to preclude a recurrence shall be submitted in the Semiannual 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 l
levels which are 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 radi,o-t logical change in the surrounding environment.
l 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.
Unit 1 - Amendment No.97 1
15.7.7-3 Unit 2 - Amendment No.101 y
1 i
The Icnd in the area of Point B2ech Nuclear Plant is used prisarily for farming and dairy operations. Therefore, radiological environmental samp1-ing of vegetation is conducted to detect changes in radiological conditions at the base of the food chain. Sampling of area-produced milk is carried out because dairy farming is a major industry in the area.
Water, periphyton, and fish are analyzed to monitor radionuclide levels in Lake Michigan in the vicinity of PBNP. Periphyton, attached algae, concen-trate radionuclides from the surrounding lake water. Therefore, algae samples, along with lakewater samples, provide a means of detecting changes which may have a potential impact on the radionuclide concentrations in Lake Michigan fish. Because of the migratory behavior of fish, fish sampling is of minimal value for determining radiological impact specifically related to the operation of the Point Beach Nuclear Plant. However, fish sampling is carried out as a conservative measure with emphasis on species which are of intermediate trophic level and which exhibit minimal migration in order to monitor the status of radioactivity in fish.
Vegetation, algae, and fish sampling frequencies are qualified on an "as available" basis recognizing that certain biological samples may occasionally be unavailable due to environmental conditions.
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Unit 1 - Amendment No. 97 15.7.7-4 Unit 2 - Amendment No. 101
TABLE 15.7.7-1 gg OPERATIONAL RADIOLOGICAL ENVIRONMENTAL PROGRAM e e FE
..EE -
NUMBER & LOCATION OF COLLECTION ANALYSIS TYPE l
SAMPLE TYPE SAMPLES FREQUENCY AND FREQUENCY 22 PP Direct environmental 23 TLDs are distributed as follows:
Quarterly Gamma dose quarterly (Each TLD contains 2 chips)
%S" 9 - In the general area of the site boundary in the nine meteor-logical sectors around the Point Beach Nuclear Plant 1 - On the Lake Michigan side of PBNP 11 - In a ring around PBNP at a distance of 3 to 6 miles from the plant 1 - Background reference in a low D/Q area greater than 10 miles from PBNP 1 - Transport control Vegetation 8 samples of vegetation obtained as 3x/yr as Radioiodine and gamma isotopic analysis follows:
available performed 3x/yr as samples are available 1 - Background reference as de-scribed above 4 - In the general area of the site boundary
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3 - At locations N, W and S of PBNP
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at 3-6 miles from the plant i
TABLE 15.7.7-1 (Continued) gijf ne h3 -d e o 3p37 NUMBER & LOCATION OF COLLECTION ANALYSIS TYPE gg SAMPLE TYPE SAMPLES FREQUENCY AND FREQUENCY au EIE! Well water 1 - Onsite well Quarterly H-3 quarterly with gamma isotopic analysis performed quarterly on total gppy solids 50 Lake water 1 - Discharge flume Monthly Monthly gross beta and gamma isotopic (discharge analysis of total solids.
H-3 analysis 2 - N of discharge 0.5 to 5 fiume is quarterly on composite alles from PBNP collected weekly and 2 - S of discharge 0.5 to 5 composited miles from PBNP for monthly analysis)
Air filters 1 - Reference location as de-Weekly by Radioiodine weekly on charcoal canisters.
scribed above continuous Gross beta weekly on particulate filters air sampler after at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> decay.
Gamma 4 - In the general area of the isotopic analysis quarterly on particulate site boundary filter composites.
1 - About 6 miles W of PBNP Milk 3 - Dairy farms about 2-6 miles N, Monthly Monthly gamma isotopic analysis and W, and S of PBNP radioidine analysis Fish 1 - Travelling screens 3x/yr as Gamma isotopic analysis 3x/yr as avail-available able.
Analysis of edible portinns only Algae 2 - Along shore within 5 miles 3x/yr as Gross beta and gamma isotopic analysis N and S of discharge available 3x/yr as available
I TABLE 15.7.7-2 RADIOLOCTCAL ENVIRONMENTAL NONITORING ANALYSIS EE LOWER LIMIT OF DETECTION (LLD)2 "A.
WellWaterg Milk Lake Water Algae Fish Vegetation Airborge f f Analysis (pC1/g vet)
(pcl/m )
(pci/1)_
(pC1/1)-T.S.4 (pci/g vet)
(pCi/g vet) 4 0.25 0.01 Cross Beta ss 3,000 H-3 oo',
Camma Scan ou I-131 0.06 0.07 0.5 Cs-137 0.08 0.06 18 18 0.25 0.15 Cs-134 0.06 0.05 15 15 0.25 0.13 15 0.25 0.13 Co-58 15 0.25 0.13 Co-60 15 15 Ba-La-140 15 Zr-Nb-95 30 0.26 Fe-59 30 0.26 Zn-65 15 0.13 Mn-54 e
4 W
NOTES FOR TABLE 15.7.7-2 EF EF For gamma isotopic analysis of environmental samples, the spectrum is scanned over the energy 1.
range of 80 to 2048 kev for gamma ray emitting radionuclides which may be attributable to Point Beach The analysis specifically includes, but is not limited to Mn-54, Fe-59, Zn-65, no _.
Nuclear Plant effluents.
Co-58, Co-60, Zr-Nb-95, Ru-103, Ru-106, I-131, Ba-La-140, Cs-134, Cs-137, Cc-141, and Cc-144.
![![
2.
The environmental TLDs have an LLD of 1 mrem / chip.
RR j' R 3.
No drinking water zz oP 4.
T.S. = total solids E$$
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5
TABLE 15.7.7-3 RADIOLOGICAL ENVIRONMENTAL MONITORING ANALYSIS EE NOTIFICATION I.EVELS a-r+ c+
N =*
Well Water &
Milk I.ake Water Algae Fish 8E Vegetation.
Afrhorge Analysis (pC1/g wet)_
(pci/m )_
(pC1/1)
(pci/1)-T.S.
(pC1/g wet)
(pCi/g wet) 30,000 m$
H-3 c+ r+
0.1 0.9 3
20 70 50 10 2
Cs-134 1
10 60 30 10 1
1,000 10 30 Co-58 300 10 10 Co-60 300 200 Ba-La-140 400 Zr-Nb-95
-10 400 Fe-59 20 300 Zn-65 30 1,000 Mn-54
)
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15.7.8 ADMINISTRATIVE CONTROLS 15.7.8.1 Responsibilities of the Manager's Supervisory Staf f The responsibilities of the Manager's Supervisory Staff with respect to these radiological effluent technical specifications are listed in specification 15.6.5.2.6 at items k and 1.
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 at least once every 24 months 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 at least once every 12 months utilizing either offsite licensee personnel or a qualified consulting firm.
C.
The results of the audits in A and B above shall be trans-mitted to the Vice-President - Nuclear Power and the Chairman of the Offsite Review Committee.
15.7.8.3 Plant Operatina Procedures The ODCM and the PCP shall be established and maintained in 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 Requirements
}
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, D.C. 20555 within the time periods specified.
A.
Semiannual Monitorina Report A report within 60 days after January 1 and July I each year for the six month period or fraction thereof, ending June 30 and December 31 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 Unit 1 - Amendment No. 97 15.7.8-1 Unit 2 - Amendment No.101 l
t within the limits of 10 CFR 20 shall be provided (sum-marized on a monthly basis) as follows:
a.
Liquid Releases (1) Total radioactivity (in Curfes) released, other than tritium, and average dtluted discharge concentrations.
(2) Total tritium (in Curies) discharged, and average diluted discharge concentrations.
(3) Total volume (in gallons) of liquid waste released into circulating water discharge.
(4) Total volume (in gallons) of dilution water used.
(5) The maximum concentration released (averaged over the period of a single release).
(6) Estimated total radioactivity (in Curies) released, by nuclide (other than tritium),
based on representative isotopic analyses performed.
b.
Gaseous Releases (1) Total radioactivity (in Curies) released of:
(a) Noble Gases.
(b) Halogens.
(c) Particulates (d) Tritium.
(2) Maximum release rate (for any one-hour period).
(3) Estimated total radioactivity (in Curies) re-leased by nuclide (other than tritium) based on representative isotopic analyses performed.
c.
Solid Waste
)
(1) The total amount of solid waste shipped (in l
cubic feet).
(2) Estimated total radioactivity (in Curies) involved.
J (3) The dates of shipment.
2.
New and Spent Fuel Receipts and Shipments Number and type of new fuel assemblies received during a.
the reporting period, if any.
1 1
Unit 1 - Amendment No. 97 15.7.8-2 Unit 2 - Amendment No.101 l
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Number of spent fuel assemblies shipped off site b.
during the reporting period, if any.
Environmental Monitoring 3.
A summary of pertinent environmental non-s.
itoring activities performed during the reporting period, including:
The number and types of samples taken and the (1) types of analytical measurements made on the samples.
Any changes made in sample types or locations (2) during the reporting period and criteria for these changes.
A summary of survey results during the reporting b.
period including a comment on any significant portion of the Operational Environmental Monitoring Program not conducted.
4.
Leak Testing of Sealed Sources Results of required leak tests performed on sealed sources if the tests reveal the presence of 0.005 microcuries l
or more of removable contamination.
5.
Meteorological Data Meteorological data shall be kept in file on site for The data available will review by the NRC upon request.
include wind speed, wind direction, atmospheric stability, The data will be in the and precipitation (if measured).
form of strip charts, hour-by-hour averages listed on magnetic tape or joint frequency distributions of each The magnetic of the parameters except precipitation.
tape and joint frequency distributions will be available following the installation and operation of the new plant process computer and software (approximately 1987).
6.
ODCM and PCP Channes A description of changes to the ODCM or PCF which were implemented and became effective during the reporting The description shall include sufficient period.
information to support the rationale for the changes Unit 1 - Amendment No. 97 Unit 2 - Amendment No. 101 15.7.8-3
and a determinacion that the change will not reduce p
the overall effectiveness of the PCP or ODCM. For the ODCM, this submittal shall include revised ODCM pages affected by the change identified with a revision number and approval date.
m 7.
Special Circumstance Reports In accordance with note 7 to Table 15.7.3-1, if a.
the Waste Gas Holdup System Explosive Gas Monitor is out of service for greater than 14 days, b.
In accordance with 15.7.7.B.3, factors which render the LLDs stated in Table 15.7.7-2 un-achievable.
In accordance with 15.7.7.E.2, f ailure of the c.
analytical laboratory to participate in an Interlaboratory Comparison Program.
3.
Measured Radioactivity Above Notification Levels If the confirmed level of radioactivity remains above the notification levels specified in Table 15.7.7-3 of specification 15.7.7 " Operational Environmental Monitoring Program", a written re-port describing the circumstance shall be prepared and submitted within thirty days of the confirma-tien that a notification level was exceeded, i
C.
Radioactive Liquid Ef fluent Treatment If the radioactive liquid effluent treatment system is inoperable and liquid effluents are being discharged for 31 days without the treatment required to meet the relear. limits specified in Section 15.7.5, 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.
2.
Actions taken to restore the inoperable equip-ment to operable status.
Unit 1 - Amendment No. 97 15.7.8-4 Unit 2 - Amendment No.101
3.
Su= mary description of actions taken to prevent a a
recurrence.
D.
Radioactive Gaseous Effluent Treatment If the radioactive gaseous ef fluent treatment system is inoperable and gaseous effluents are being discharged 8
the for 31 days without the treatment required to meet release limits specified in Section 15.7.5, 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 i
or subsystem and the reason for inoperability.
2.
Actions taken to restore the inoperable equip-ment to operable status.
3.
Summary description of actions taken to pre-vent a recurrence.
E.
Radioactive Effluent Releases If the quantity of radioactive caterial actually released in liquid or gaseous effluents during any calendar quarter exceeds twice the quarterly limit as specified in Section 15.7.5, a special report shall be prepared and submitted to the Commission within thirty days of determination of the release quantity.
15.7.8.5 Major Change to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems Licensee initiated major changes to the radioactive waste treat-ment 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 svamary of.the evaluation that led to the determination A.
that the change could be made in accordance with 10 CFR Part 50.59; Information necessary to support the reason for the change; B.
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Unit 1 - Amendment No. 97 l
15.7.8-5 Unit 2 - Amendment No.101
C.
A description of the equipment, components and processes
)
involved and the interfaces with other plant systems; a
An evaluation of the change, which shows how the predicted D.
releases of radioactive materials in liquid effluents and gas'eous effluents and/or quantity of solid waste will differ from those previously predicted in the license application and amendments thereto; An evaluation of the change, which shows the expected max-E.
imum exposures to an individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto; An estimate of the exposure to plant operating personnel F.
as a result of the change.
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l Unit 1 - Amendment No. 97 15.7.8-6 Unit 2 - Amendment No.101
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