ML20054E722
| ML20054E722 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/28/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20054E717 | List: |
| References | |
| TAC-48383, NUDOCS 8206140107 | |
| Download: ML20054E722 (18) | |
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UNITED STATES
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NUCLE AR REGULATORY COM' ISSION M
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.e p WASHINGTON, D. C. 20555 8
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BON Certified B OV NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY TriE 'IARTFORD ELECT'RIC LIGHT COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. OPR-21 1.
The Nuclear Regula' tory Comission (the Comission) has found that:
The application for amendment by Northeast Nuclear Energy Company, A.
et al. (the licensee)' dated May 14, 1982, 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 conformity 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 I
conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common r
l defense and security or to the health and safety of the public; and i
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.
8206140107 820528 DR ADOCK 05000
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's Accordingly, the license is amended by changes to the Iechnical.
2.
Specifications as indicated in the attachment to this license
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amendment, and paragraph 3.(B) of Facility Operating License ff No. OPR-21 is hereby amended to read as follows:
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u (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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Thislicenseamendment,iseffectiveasofthedateof-itsihduagce.
3.
FOR THE NUCLEAR' REGULATORY C0FMISSION
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Dennis M. Crutchfield, Ch ef j
Operating Reactors Branch #5 T
Division of Licensing
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Attachment:
Changes to the Technical Specifications 5
Date of Issuance:
May 28, 1982 s'
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ATTACHMENT TO LICENSE AMENDMENT NO. 84
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FACILITY OPERATING LICENSE NO. DPR-21 DOCKETcN0. 50-245 i
Remove and replace the following pa,ges of the Appendix B Environmental
- Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and c'ontain vertical lines indicating the area of change.
Remove Insert
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2,4-1,
2.4-1 2.4-3 2.4-3 2.4-4 2.4-4 2.4-5 2.4-5 2.4-15 2.4-15 2.4-16 2.4-16 is fr'
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j 2.4 Radioactive Effluents 2.4.1 Liquid Waste Effluents 2.4.1.1 Objective To define the limits of conditions for the controlled release of radioactive materials in liquid effluents to the environs to ensure that these releases are as low as practicable.
2.4.1.2 Specification A.
The concentration of radioactive materials released in liquid waste effluents from all reactors at the site shall not exceed the values specified in 10 CFR Part 20, Appendix B. Table II, Column 2, for unrestricted areas.
If this limit cannot be met, radioactive effluents shall not be released.
.w B.
The equipment installed in a particular liquid radio-active waste stream shall be maintained and shall be operated to process radioactive liquid wastes prior to their discharge when the projected quarterly in-dividual dose due to liquid effluent releases from that particular waste stream would exceed 0.1 MREM to the whole body or 0.3 MREM to any organ.
C.
If the quarterly dose to an individual from a unit's liquid effluents exceeds 1.0 MREM to the whole body or 3.0 MREM to any organ, the licensee shall make an investigation to identify the causes of such releases, define and initiate a program of action to reduce such releases to design objective levels and report these actions to the Commission within 30 days from the end of the quarter during which the release occurred.
D.
The dose to an individual from a unit's liquid effluents shall not exceed 1.5 MREM to the whole body or 5 MREM to any organ during a calendar quarter.
E.
The dose to an individual from a unit's liquid effluent shall not' exceed 3.0 MREM to the whole body or 10 MREM to any organ in any 12 consecutive months.
F.
Except as specified in 2.4.1.3.C. during release of radioactive wastes, the effluent control radiation monitor shall be set to alarm and to initiate the automatic closure of each waste isolation valve prior to exceeding the limits specified in 2.4.1.2.A.
-G.
The maximum radioactivity that may be contained in any of the following tanks shall not exceed 10 Ci, excluding tritium and dissolved gases:
Unit 1 2.4-1
. Amendment No. 84 Unit 2 Amendment No. 77
F.
The radioactivity in the steam generator blowdown and condensate polishing evaporator distillate from Unit 2 shall be monitored and recorded. Whenever the blowdown or distillate monitors are.inoper,-
able, any unmonitored blowdown flow shall be diver'ted to the waste management system or the condensate polishing waste neutralizing sumps respectively, and the direct release to the environment te rminated.
G.
Plant records shall be maintained of the radioactive concentration and volume before dilution of liquid waste intended for discharge, and the average dilution flow and length of time over which each discharge occurred.
H.
Failure to comply with Sections 2.4.1.3.A through 2.4.1.3.G re-quires prompt reporting as specified in Section 5.6.2.a.(1).
t I.
Dose calculations to ensure compliance with Specifications 2.4.1.2.B,l through 2.4.1.2.E will be performed using measured curie releases and the NRC computer code LADTAP.* These calculations shall be performed within 30 days from the end of each quarter, unless more than 1 curie (excluding tritium and dissolved gases) of activity ~
was released from a ' articular unit during a month, in which case they p
will be performed within 10 days from the end of the month for that unit.
Bases The release of radioactive materials in liquid waste to unrestricted areas shall not exceed the concentration limits specified in 10CFR Part 20 and should be as low as practicable in accordance with the require-ments of 10CFR Part 50.36a. To ensure that the releases of radioactive material above background to unrestricted areas will be as low as prac-ticable as defined in Appendix I to 10CFE Part 50, the following design I
objective has been applied:
A.
The annual dose above background to the total body or any organ of an individual from a reactor shall'not exceed 3 mrem or 10 mrem, respectively in an unrestricted area.
These specifications, while providing reasonable assurance that the resulting annual exposure to the total body or any organ of an individual in an unrestricted area is as low as practicable, permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentra-tion limits specified in 10CFR Part 20.
It is expected that by using this operational flexibility under unusual operation conditions, and exertin,g every effort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the concentration, limits specified in 10CFR Part 20.
- The LADTAP code shall be used in accordance with NNECO procedure RAB-4-3, Rev..O, dated November 1979.
Unit 1 2.4-3 Amendment No. 84 Unit 2 Amendment No. 77
1
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The design objectives have been developed based on operating experience taking into account a combination of variables including defective fuel,
~
primary system leakage, and the performance of the various waste trest-ment systems, and are consistent with Appendix I to 10 CFR Part 50.
Specification 2.4.1.2.A requires the licensee to limit the concentration of radioactive materials in liquid wastes from the site to levels speci-fied in 10 CFR Part 20, Appendix B, Table II, Column 2, for unrestricted areas. This specification provides assurance that no member of the general public will be exposed to liquid containing radioactive materials in excess of limits considered permissible under the Commission's Rules and Regulations.
Specifications 2.4.1.2.D and 2.4.1.2.E establish the upper limits for the dose due to the release of radioactive materials in liquid effluents.
I The intent of these Specifications is to permit the' licensee the flexi-bility of operation to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the levels normally achievable when the plant and the liquid waste treatment systems are functioning as designed.
Releases of up to these limits will result in concentrations of radio-active material in liquid wastes at small percentages of the limits specified in 10 CFR Part 20.
Specification 2.4.1.2.F requires that suitable equipment to control and monitor the releases.of radioactive materials in liquid wastes are operating during any period these releases are taking place consistent with the requirements of 10 CFR Part 50, Appendix A, Design Criterion 64.
Specification 2.4.1.2.B requires that the licensee maintain and operate the equipment installed in the liquid waste systems to reduce the release of radioactive materials in liquid effluents to as low as practicable consistent with the requirements of 10 CFR Part 50.36a. Normal use and maintenance of installed equipment in the liquid waste system provides reasonable assurance that the quantity released will not exceed the design objective. In order to keep releases of radioactive materials as low as practicable, the specification requires, as a minimum, operation of equipment in a particular waste stream whenever it appears that the projected doses due to releases from that particular waste stream will exceed 10% of the design objectives. This specification does not apoly to any waste stream for which a waste treatment system is not required to meet tin Appendix I criterin (l.o. Ifn l t No. ? *;t cam Generat or Blowdown).
Specifration 2.4.1.2.0 limits the amount of radioactive material that could be inadvertently released to the environment to an amount that will not exceed the Technical Specification limit.
In addition to these limiting conditions for operation, the reporting requirements of Specification 2.4.1.2.C delineate that the licensee Unit 1 2.4-4 Amendment No. 84 Unit 2 Amendment No. 77
1 shall identify the cause whenever the dose due to release of radioactive materials in liquid wastes exceeds 1.0 mrem to the whole body or 3.0 mrem to any organ during any calendar quarter and describe the proposed program of action to reduce such releases to design objective levels on a timely basis. This report must be filed within 30 days following the calendar quarter in which the release occurred.
The monitoring requirements given under Specification 2.4.1.3 provide assurance that radioactive materials in liquid wastes are properly controlled and monitored in conformance with the requirements of Design Criteria 60 and 64. These requirements provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive liquid wastes released to the environment. Reports on the quanities of radioactive materials released in liquid wast ~es are fur-nished to the Commission according to Section 5.6.1 of these Technical Specifications in conformance with Regulatory Guide 1~.21:
On the basis of such reports and any additional information the Commisssion may obtain from the licensee or others, the Commission may, from time to time, require the licensee to take such action as the Commission deems appropriate.
Monitoring Requir ements 2.4.1.3.A through E and G and H. will apply to the Condensate Polishing Weste Neutralizing Sump djscharges only when the steam generator gross activity exceeds 1 x 10 pCi/ml. Discharges from these sumps will be terminated when the Steam Generator or the S.J.A.E. Radiation Monitors alarm, until Monitoring Requirements 2.4.1.3.A through E and G and H are met.
l Monitoring Requirements 2.4.1.3.E through H will apply to the condensate polishing evaporator distillat9 discharges only when the Steam Generator gross activity exceeds 1 x 10 pCi/ml. If the monitoring requirements of 2.4.1.3.E through H are not met, discharges from this pathway will be terminated when the Steam Generator Blowdown or the S.J.A.E.' Radiation Monitors alarm.
The points of release to the environment to be monitored in Section 2.4.1 include all the monitored release points as provided for in Table 2.4-3.
Monitoring Requirement 2.4.1.3.I ensures that the determination of dose based on measured curie releases is consistent with NRC Regulatory Guide 1.109, Revision 1.
y.
Unit 1 2.4-5 Amendment No. g4 untt ?
Amendment No. 77
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Tcblo 2.4-1 5
RADI0 ACTIVE LIQUID SAMPLINC AND ANALYS13 1
l Liquid j
Source sampling Type of Detcetable Frequency Activity Analysia -
Concentrations (pC1/el)(3)
A.
Monitor Tank Releases, Each Batch and/or Condensate Principal Canma Emitters S x 10' I'
Po11ehing Weste.Neu-One Bateh/Honth
}
t.ralizing Susp Re-Dissolved Cases _
3 10 leases (7)
Weekly comedm?.te Be-I.a-140, 1-131 10-6 Sr-89
[.x _10_4
_ Monthly compositeII H-3 10'I i
Crose Alph'a 10'I Quarterly Cc asiteIII a
b St-90 5 m 10'8 B.
Deleted C.
Steam Cenerator Blowdown Weekly (6)
Principal Cause Emitters S x 10' IN (Unit 2 only)
Condensate Polishing Ba-La-140, 1-131
- 10'0 -
only)
One semple / Month Dissolved Cases 10-5 n
i Sr-89 S x 10'I Monthly compositeII H-3 1
10-5 Crose alpha 10'I.,
Quarterly Campoette $}
Sr-96
' S w 10'__8 I
DPR-21: Amsndment No. 3[,48,JJ 84 DPR-65:' dinendment No. 143'40, 44, 77
Table 2.4-1 (Continued)
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. (1)
A composite saeple is one in which the quantity of liquid _ sampled is proportional to the quantity of liquid wasta disi.harged.
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~ (2)
For certain mixture: of gaz=a emittprs, it may not be possible to measure l
radionuclides in concentrations near their sensitivity limits when other-nuclides are present in the sample in much greater concentrations. Under these circumstances, it vill be more appropriate to calculate the concentrati of such radior.uclides using measured ratios with those radionuclides which are routinely identified and measured.
(3)
The detectability'11mits for activity analysis are based on ihe technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lover detection limits may be readily achievable and when nuclides are measured below the stated 11=its, they shall also be reported.
(4)
Deleted (5)
To be representative of the average quantities and concentrations of radio-active materials in liquid effluents, samples should be collected in pro-portion to the rate of flow of the effluent, stream., Frior to analyses, all samples' taken for the co=posite should be, thoroughly mixed in order for the composite.sa=ple to be representative of the average affluent release.
(6)
These ana' lyses are required when the stein generator gro'ss activity (sa= pled and analyzed 3 times per week as per the Safety Technical Specifications Table 4.7-2) exceeds 1 1 10 7 p Ci/al.
-(7)
Sa=pling and analysis of the Condensate Polishing Veste Neutralizing Sumps.and the Condensate Polishing Evapcirator Distillate, for the l
activity analysis shown in Table 2.4.1, are reguired only when the steam generator gross activity exceeds 1 x 10- pCi/ml.
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t a.
2.4-16 DPR-21: Amendment No. 3d., M, 55, 84 DPR-65: Ame'ndment No'. ~{4, /4,, '4 4, 77
p reg,,
'o UNITED STATES 8
N NUCLEAR REGULATORY COMMISSION 5
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WASHINGTON, D. C. 20555 k
DESI ' TED ORIGINAL
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Certified c;v t
NORTHEAST NUCLEAR ENERGY COMPANY' THE CONNECTICUT LIGHT AND POWER COMPANY THE HARTFORD ELECTRIC LIGHT COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT N0. 2
.m AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 77 License No. DPR-65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated May 14, 1982, 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 (1) that the activities authorized by this amendment can be conducted without endangering the health r.
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.
e e
Accordingly, the license is amended by changes to.the Yechnical 2.
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 77, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f&
WA, Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical'
. Specifications Date of Issuance: May 28, 1982 m
-e e
e
ATTACHMENT TO LICENSE AMENDMENT N0. 77, FACILITY OPERATING LICENSE NO. OPR-65 DOCKET NO. 50-336 Remove.and replace the following pages of the Appendix B Environmental Technical Specifications.with the enclosed pages.
The revised pages are identified by Amendment number and. contain vertical lines indicating the area of change.
Remove Insert 2.4-1 2.4-1
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2.4-3 2.4-3 2.4-4 2.4-4 2.4-5 2.4-5
.2.4-15 2.4-15 2.4-16 2.4-16 P
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2.4 Radioactive Effluents 2.4.1 Liquid Waste Effluents
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J-2.4.1.1 Obiective Tr define the limits of conditions for the controlled release of radioactive materials in liquid effluents to the environs to ensure that these releases are as low as practicable.
..a.L Specification A.
The concentration of radioactive materials released in liquid waste effluents from all reactors at the site shall not exceed the values specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for unrestricted areas.
If this limit cannot be met, radioactive effluents' shall not be released.
B.
The eq'uipment installed in a particular liquid radio-active waste stream shall be maintained and shall be operated to process radioactive liquid wastes prior to their discharge when the projected quarterly in-dividual dose due to liquid effluent releases from that particular waste stream would exceed 0.1 HREM to the whole body or 0.3 MREM to any organ.
If th,e quart.erly dose to an individual from a unit,'s,
C.
liquid effluents exceeds 1.0, MREM to the whole body or 3.0 MREM to any organ, the licensee shall make an,
investigation to identify the causes of such releases, define and initiate a program of action to reduce such releases to design objective levels and report these actions to the Commission within 30 days from the end of the quarter during which'the release occurred.
D.
The dose to an individual from a unit's liquid effluents shall not exceed 1.5 MREM to the whole body or 5 MREM to any organ during a calendar quarter.
The dose,to an individual from a unit's liquid effluent E.
shall not exceed 3.0 MREM to the whole body or 10 MREM to any organ in any 12 consecutive months.
F.
Except as specified in 2.4.1.3.C, during release of radioactive wastes, the effluent control radiation monitor shall be set to alarm and to initiate the automatic closure of each vaste isolation valve prior to exceeding the limits specified in 2.4.1.2.A.
^
G.
The maximum radioactivity that may be contained in any of the following tanks shall not exceed 10 C1, excluding tritium and dissolved gases:
Unit 1 2.4-1 Amendment No. 84 Unit 2 Amendment No. 77
e
'F.
The radioactivity in the steam generator blowdown and condensate polishing evaporator distillate from Unit 2 shall be monitored and recorded. Whenever the blowdown or distillate monitors are inoper-able, any unmonitored blowdown flow shal1 be diverted to-the waste ~
management system or.the condensate polishing waste neutralizing sumps respectively, and the direct release to the environment terminated.
G.
Plant records shall be maintained of the radioactive concentration and volume before dilution of liquid waste intended for discharge, and the average dilution flow and length of time over which each discharge occurred.,
H.
Failure to' comply with Sections 2.4.1.3.A through 2.4.1.3.G re-quires prompt reporting as specified in Section 5.6.{.a.(1).
Dose calculations to ensure compliance'with Speciffcations 2.4.1.2.1
~
I.
through 2.4.1.2.E will be perform.ed using measured curie releases and the NRC computer code LADTAP.* These calculations shall be performed within 30 days from the end of each quarter, unless more than I curie (excluding tritium and dissolved gases) of activity was released from a particular unit dur'ing a. month, in which cise el will be performed within 10 days from the end of the month for that unit.
Bases The release of radioactive materials in liquid waste to unrestricted areas shall not exceed the concentration limits specified in 10CFR Part 20 and shou'ld be as low as practicable in accordance with the require-ments of 10CFR Part 50.36a. To ensure that the releases of r'adioactive material above background to unrestricted areas will be as low as prac-ticable as defined in Appendix I to 10CFR Part 50, the following design i
objective has been applied:
The annual dose above background to the total body or any organ of A.
an individual from a reactor shall not exceed 3 mrem or 10 mrem, respectively in an unrestricted area.
These specifications, while providing reasonable assurance that the resulting annual exposure to the total body or any organ of'an individa in an unrestricted area is as low as practicable, permit the flexibilit:
of operation, compatible with considerations of. health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentra-tion limits specified in 10CFR Part 20.
It is expected that by using' this operational flexibility under unusual operation conditions, and exerting every ef fort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the concentration limits specified in 10CFR Part 20.
- The LaDTAP code shall be used in accordance with UNECO procedure RAB-4-3, Rev.,0, dated November 1979.
Unit 1 2.4-3 Amendment No. 84 Amendment No. 77 Unit 2
The design objedtives have been developed based on operating experience taking into account a combination of variables including defe.ctive fuel, primary system leakage, and the performance of the various waste treat-ment systems, and are consistent with Appendix I to 10 CFR Part 50.
Specification 2.4.1.2.A requires the licensee to limit the concentration of radioactive materials in liquid wastes from the site to levels speci-fied in 10 CFR Part 20, Appendix B, Table II, Column 2, for unrestricted This specification provides assurance that no member of the areas.
general public will be exposed to liquid containing radioactive materials in excess of limits considered permissible under the Commission's Rules and Regulations.
~
Specifications 2.4.1.2.D and 2.4.1.2.E establish the upper limits for -
the dose due to the release of radioactive materials in liquid effluents.
The intent of these Specifications is to permit the licensee the flexi-bility of operation.to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the levels normally achievable when the plant and the liquid waste treatment systems are functioning as designed.
Releases of up to these limits will result in concentrations of radio-active material in liquid wastes at small percentages.of the limits specified.in 10 CFR Part 20.
~
Specification 2.4.1.2.F requires that suitable equipment to control and monitor the releases of radioactive materials in liquid wastes are,
operating during any period these releases.are taking place consistent with the requirements of 10 CFR Part 50, Appendix A, Design Criterion 64.
Specification 2.4.1.2.B requires that the licensee maintain and operate the equipment installed in the liquid waste systems to reduce the release of radioactive materials in liquid effluents to as low as practicable consistent with the requirements of 10 CFR Part 50.36a.
Normal use and maintenance of installed equipment in the liquid waste system provides reasonable assurance that the quantity released will not exceed the design objective.
In order to keep releases of radioactive materials as low as practicable, the specification requires, as a minimum, operation
~~
of equipment in a particular waste stream whenever it appears that the projected doses due to releases from that particular vaste stre'm will a
exceed 10% of the design objectives. This specification does not apoly to any waste stream for which a waste treatment system is not required to meet the Appendix I criteria (i.e. Unit No. 2 Steam Generator Blowdown).
Specifcation 2.4.1.2.G limits the amount of radioactive material that could be inadvertently released to the environment to en amount that will not exceed the Technical Specification limit.
In addition to these limiting conditions for operation, the reporting requirements of Specification 2.4.1.2.C delineate that the licensee Unit 1 2.4-4 Amendment No. 84 Unit 2 Amendment No. 77 a
shall identify the cause whenever the dose due to release of radioactive materials in liquid wastes exceeds 1.0 mrem to the whol,e body or 3.0 mrem to any organ during any calendar quarter add describe the proposed program of action to reduce such releases to design objective levels on a timely basis. This report must be filed within 30 days following the calendar quarter in which the release occurred.
The monitoring requirements given under Specification 2.4.1.3 provide assurance that radioactive materials in liquid wastes are properly controlled and monitored in conformance with the requirements of Design Criteria 60 and 64. These' requirements provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive liquid wastes released to the environment. Reports on the quanities of radioactive materials released in liquid wast'es are' fur-nished to the Commission according to Section 5.6.1 of'these, Technical Specifications in conformance with Regulatory Guide l'.21:
On the basis of such reports and.any additional information the Commisssion may obtain from the licensee or others, the Commission may, from time to time, require the licensee to take such action as the Commission deems appropriate.
Monitoring Requir ements 2.4.1.3.A through E and G and H. will apply to theCondensatePolishingWasteNeutralizingSumpdjschargesonlywhen the steam generator gross activity exceeds _1 x 10 pCi/ml. Discharges from these sumps will be terminated when the Steam Generator or the S.J. A.E. Radiation Monitors alarm, until Monitoring Requirements. 2.4.1.3. A through E and G and H are met.
Monitoring Requirements 2.4.1.3.E through H will apply to the condensate polishing evaporator distillat9 discharges only when the Steam Generator gross activity exceeds 1 x 10 pCi/ml.
If the monitoring requirements of 2.4.1.3.E through H are not met, discharges from this pathway will be terminated when the Steam Generator Blowdown or the S.J.A.E. Radiation Monitors alarm.
The point's of release to the environment to be monitored in Section 2.4.1 include all the monitored release points as provided for in Table i
j-2.4-3.
l Monitoring Requirement 2.4.1.3.I ensures that the determination of dose based on measured curie releases is consistent with NRC Regulatory Guide l
1.109, Revision 1.
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2.4-5 Amendment No. g4 Unit 1 Amendmant No. 77 Unit 2
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l
(
m y
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t A
ST B
a y
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Rnss tl oil t
an PD n keau ro O
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n
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- ~
Table 2.4-1 (, Continued')
(1)
A co=posite sanple is one in which the quantity of liquid sa= pled is proportional to the quantity of liquid vaste, discharge.d.
- ~_
(2)
For certain mixture: of ga.=na ccittprs, it u.ay not be possibic to neasure radionuclides in concentrations near their sensitivity li=its when other nuclides are 1 resent in the sa=ple in much greater meentrations. Undet 5
these circunstances, it vill be more appropriate tu calculate the concent of such radionuclides using measured ratios with those radionuclides whic are routinely. identified and s>easured.
(3)
W.e detectability linits for activity analysis are based on ihe technical feasibility and on the potential significance in the environ =ent of the quantities released. For sone nuclides, l'over detection li=1ts say,be readily achievcble and when nuclides are measured below the stated 2 4'ts they shall also be reported.
(4)
Deleted (5)
To be representative of the average quantities and concentrations of rad:
active materials in liquid effluents, samples should be collected in pro-portion to the rate of flov of the effluent. stream., Prior to analyses..
sanples' taken for the ce=posite should be,ther,oughly mixed in order for C ce=posite sa=ple to be representative of the average effluent releace.
~
(6)
These analyses are required when the s,tein generator gross activity (sa.: pled and analyzed 3 ti=es per week as per the Safety Technical Specifications Table 4.7-2) exceeds 1 I.10 7 p Ci/ml.
-(7)
Sa=pling and analysis of the Condensate Polishing Vaste Neutralizing Su=ps.and the Condensate Polishing *Evapo'rator Distillate, for the activity analysis shown in* Table 2.4.1, are recuired only when the steam generator gross activity exceeds 1 x 10 7 pC1/ml.
2.4-16
~
e DPP-21: Amendment No. 30., f8, 55,84
~~~
DPR-65: Ame'ndment No'. *(4, f,d, 'f f, 77
_ _ _