ML20094S279

Proposed Tech Specs Re Radiological Effluent TS Conformance

ML20094S279
Person / Time
Site:	Prairie Island
Issue date:	11/28/1995
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20094S271	List: ML20094S270 ML20094S279
References
NUDOCS 9512060099
Download: ML20094S279 (14)

Text

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SUPPLEMENT to LICENSE AMENDMENT REQUEST Dated July 17,1995 Radiological Effluent Technical Specification Conformance To Standard Technical Specifications and Generic Letter 89-01 ATTACHMENT 1 Appendix A, Technical Specifications Marked Up Pages TS-ix TS.6.5-2 TS.S.5-3 TS.6.5-5 TS.6.5-7 TS.6.5-7 Overflow TS.6.7-6 9512040099 951128 PDR ADCCK 05000282 P.m..

._..PDR

TS-ix REV 11':

1/11/95 TABLE OF CONTENTS (Continued)

TS SECTION-IJ,JJE PAGE 6.7 Reporting Requirements TS.6.7-1 A. Routine Reports TS.6.7-1

1. Annual Report TS.6.7-1

a. Occupational Exposure Report-TS.6.7-1

b. Report of Safety and Relief Valve Failures and Challenges TS.6.7-1

c. Primary Coolant Iodine Spike Report TS.6.7-1

2. Startup Report TS.6.7-2

3. Monthly Operating Report TS.6.7-2

4. Aasmal Radioactive Effluent Report TS.6.7-3

5. Annual Summaries of Meteorological Data TS.6.7-$4

6. Core Operating Limits Report TS.6.7-$4 B. Reportable Events TS.6.7-44 C. Environmental Reports TS.6.7.$6

1. Annual RadiQQQsle&4+n Environmental Monitoring Reports TS.6.7-}6

2. Delefsd En'zirenrental Speciel R: pert:

TS.6.' 6

3. 6thei~ Environmental Reports TS.6.7-g7 (non-radiological, non-aquatic)

D. Special Reports TS.6.7-g4 i

TS.6.5-2 PE! 70 9/12/94 1EE~f Psrssant;t6 10cs%20rp~ iriiirsph'as?' 16011syniirituiN'*hu requireenste of 10cm20.1601, each hiskxadiactos:ayegasq inef taed in' tocPaso,linm ewtotenettrerrestandarts kroater than 100 mram/hr but'Ima dpo'1000 maan/hr@~4a11:bs and entramesyther.e. heit Mens #ytted bymarricaded'and canopte etw 3

g Vaagelsii of s'Radiaties Work Permit lppFy J edividuals

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ist emehnicians) or personas 1'eentlaucusly esserted luidi individuals any be emeupt fraps bsLENP'issuense~'

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l b';"'In~ addition ^to"theregairements~'of ~$pesiffcati'o^n~'6 5!B71'!s

^ ' Above, areas with radiation levels grea'ter'than or ' equal td 1000 mrea/hr shall be provided with locked ~or' continuously 4

guarded doors'to prevent unauthorisedcentry'and'tho' keys shall~

be maintained}iunder' the administrative' controliof tho' Shif Supervisor on duty hr health physics supervision. Doors',shall, resusin locked except'during periods of access by personnel under^an approved RWP,that shellsspecLfy the dose"raterlevelis']

in'the immediate work; areas and the maximum allowable stayj tirees for' individuals'in chose areas 4In'11eu ofl the istay ti,me' specification of, the RUPv' direct, orJ remote ',(ouch as, closed 4

circuit TV or transmitting radiation monitoring; device)

' ontinnous'aurveillance 'may;be'aade by 'peraennet'qualifisa id c

' radiation protection procedures to provide' positive exposure c, ont rol ove r, the_.' ac't_ivities.b. ei.n5' P8.e. s.m._med._withi. n.m.h.,e_are.s_!

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6 2.

A program shall be implemented to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:

a. Provisions establishing preventive maintenance and periodic visual inspection requirements, and

b. Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals A program acceptable to the Commission was described in letters from L.O.Mayer, NSP, to Director of Nuclear Reactor Regulation, deced December 31, 1979 " Lessons Learned implementation" and March 13, 1980, "1/1/80 Lessons Learned Implementation Additional Information".

3.

A program shall be implemented which will ensure the capability to accurately determine the airborne iodine concentration in ersential plant areas under accident conditions. This program shall include the following:

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Offsite Dose Calculation Manual (ODCM)

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balculation of offsite doses resulting from'rsdioactive gaseous and liquid effluents, in the calculation of gaseous and liquid offluent; monitoring alarm and trip setpoints, and in4tho' conduct of the

'radiologicalenvironmentalmonitoringprogram.The'0DQt,shallialisj contain the radioactive effluent controls and radi41ogical

' environmental monitoring activities and' descriptions of ths information that should be included in the;Annus1' Radiological

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TS.6.7-6 R"! 105 5/':/93 1

C.

Environmental Reports The reports listed below shall be submitted to the Administrator of the appropriate Regional NRC Office or his designate:

1 1.

Annual Radisi1WMatten Environmental Monitorine Report Ths_TA_n.irm dth

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':) ^ nurl R dictier Envircrc:nt:1 M nit: ring Erpert: : r rin; the ep retier,ef the pre;r.- during the previeur ::1:n' r y:cr ch:11 he submitted prier te May 1 ef cr:5 ye r.

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M--The Annual Radiation Environmental Monitoring Reports shall include summarized and tabulated results in the format of Regulatory Guide i

4.8, December 1975 of all radiclogical environmental samples taken during the report period.

In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary report.

4 1

M--The reports shall also include the following: a summary description j

of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensees participation in the I n t e rl abo ra t o ry Compar i s on Programi.ds.s.t. E. wes,.!I..<f..i%.h&,mc.<.D._e.ID CIC...n, required by sd wv o

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s Specif!: tier ^.10.C.1.

1 2.

D$14Eted E~~!ren entel S ::i 1 E:: rte (2) redieret!vity 12:21: ir cenpler enerr linit: rpecified ir Table N-e

^ 10-3, en Envircrr:nt:1 Sp::i:1 R:p rt ch:11 5: ruhnitted eithir 30 1

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l SUPPLEMENT to LICENSE AMENDMENT REQUEST Dated July 17,1995 i

Radiological Effluent Technical Specification Conformance To Standard Technical Specifications and Generic Letter 89-01 i

ATTACHMENT 2 Appendix A, Technical Specifications Revised Pages TS-ix TS.6.5-2 TS.6.5-3 TS.6.5-5 TS.6.54 TS.6.5-7 TS.6.7-5 TS.6.74 i

a i

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TS-ix 1

I TABLE'0F CONTENTS (Continued)

TS SECTION TITLE PAGE 15. 7 Reporting Requirements TS.6.7-1 A. Routine Reports TS.6.7-1

-1. Annual Report TS.6.7-1

a. ?ccoostional Exposure Report TS.6.7-1 b Repore of_ Safety and Relief Valve Failurec and Challenges TS.6.7-1

.:. Primary Cunlant Iodine Spike Report TS.6.7-1

2. Startup Report TS.6.7-2

3. Monthly Operating 20nort-TS.6.7-2

4. Radioactive Effluent Keport TS.6.7-3

~

5. Annual Summaries of Meteorological Data TS.6.7-3

+

6. Core Operating Limits Report TS.6.7-3 B. Reportable Events TS 6.7-4 C. Environmental Reports TS.6.7-5

l. Annual Radiological Environmental Monitoring Report TS.6.7-5 3'

2. Deleted

3. Other Environmental Reports TS.6.7-5 (non-radiological, non-aquatic)

D. Special Reports TS.6.7-6 l

J e

T 4

t 4

0 9

L 3

J

1 4

TS.6.5-2 t

1.

ai Pursuant to 10CFR20, paragraph 20.1601(c), in lieu of the requirements of 10C R20.1601, each high radiation area,.as-defined in 10c m20, in which the intensity of radiation is-J I

greater:than 100 mres/hr but less than 1000 mres/hr, shall be-barricaded and conspicuously posted as a high radiation area j

l' and entrance thereto shall be controlled by requiring issuance

- of a Radiation Work Permit (RWP). Individuals qualified in l

radiation protection procedures.(e.g., health physics technicians) or personnel continuously escorted by such

.[

individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high l

radiation areas with ' exposure rates less than or equal.to 1000 nres/hr, provided they are otherwise following plant; radiation

]

protection procedures for entry into such high radiation areas.

{

l

[

Any individual or group of individuals perr itted to enter such i

areas shall be provided with or accompanied by one or more of

'the following:

f l

(1) A radiation monitoring dev' that continuously indicates the radiation dose rate in the area.

'(2) A radiation monitoring device that continueusly integrates i

the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of l

,I them.

j (3) An' individual qualified in radiation protection procedures j

E with a radiation dose rate monitoring device, who is

~

responsible for providing positive control over the i

activities within the area and shall perform periodic radiation surveillance at the frequency specified by the j

radiation protection manager.

b. In addition to the requirements of Specification 6.5.B.1.a above, areas with radiation levels greater than or equal to-1000 mrem /hr shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys shall i

j,

be maintained under the administrative control of the Shift l

Supervisor on duty or health physics supervision. Doors shall remain locked except during periods of access by personnel j

under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay j

i i

4 l

i i

~

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TS.6.5-3 times for individuals in those areas. In lieu of the stay time specification of the RWP, direct or remote (such as closed

[

circuit TV or. transmitting radiation monitoring device) j continuous surveillance may be nada by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area, j

c. For individual high radiation areas with radiation levels of i

greater than 1000 mres/hr, accessible to personnel, that are located within large areas such as reactor containment, where i

no enclosure exists for purposes of. locking, or that cannot be continuously guarded, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

l 2.

A program shall be implemented to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:

Provisions establishing preventive maintenance and periodic a.

visual inspection requirements, and

b. Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals A program acceptable to the Commission was described in letters from L.O.Mayer, NSP, to Director of Nuclear Reactor Regulation, dated December 31,1979 " Lessons Learned implementation" and March 13, 1980, "1/1/80 Lessons Learned Implementation Additional Information".

3.

A program shall be implemented which will ensure the capability to accurately determine the airborne iodine concentration in l

essential plant areas under accident conditions. This program i

f shall include the following:

a. Training of personnel,

b. Procedures for monitoring, s,d

c. Provisions for maintenance of sampling and analysis equipment A program acceptable to the Commission was described in letters from L.O.Mayer, NSP, to Director.of Nuclear Reactor Regulation, dated December 31,1979 " Lessons Learned Implementation" and March 13,1980, "l/1/80 Lessons Learned Implementation Additional Information".

i l

1

4 TS.6.5-5 l

Changes to the ODCM:

.i 1.

Shall'be documented and records.of reviews performed shall'be j

retained. This documentation shall contain.

a. sufficient information to support the change (s) together with the appropriate analyses or evaluations justifying the l

change (s),

b. a determination that the change (s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 j

CFR190, 10 CFR 50.36a, and 10 CFR-50, Appendix I, and not adversely impact the accuracy or reliability of effluent,.

l dose or setpoint calculations; 2.

Shall become effective after approval by a member of plant management designated by the Plant Manager.

3.

Shall be submitted to the NRC in the form of a complete legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed. The date (i.e.,

month and year) the change was implemented shall be indicated.

F.

Security-Procedures shall be developed to implement the requirements of the Security Plan and the Security Contingency Plan. These' implementing procedures, with the exception of those non safety related procedures l

which govern work activities exclusively applicable to or performed by security personnel, shall be reviewed by the Operations Committee and approved by a member of plant management designated by the Plant Manager. Security procedures not reviewed by the Operations Committee shall be reviewed and approved by the Superintendent Security.

G. Temporary Changes to Procedures Temporary changes to Operations Committee reviewed procedures i

described in A,B,C,D.E and F above, which do not change the intent of the original procedure may be made with the concurrence of two members of the unit management staff, at least one of whom holds a Senior Reactetr Operator License. Such changes shall be documented, 3

reviewed by tihe Operations Committee and approved by a member of plant management designated by the Plant Manager within one month.

l Temporary changes to security procedures not reviewed by the l

Operations Committee shall be reviewed by two (2) individuals knowledgeable in the area affected by the procedure.

1-

i i

i TS.6.5-6 H. Radioactive Effluent Controls Program This program conforms to 10CFR50.36a for the control of radioactive l

effluents'and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable, This' program shall' allocate releases equally to each unit. The liquid radweste treatment' system, waste gas treatment system, containment purge release vent, and spent fuel pool vent are shared by both units. Experience has also shown that contributions from both units j

are released from each auxiliary building vent. Therefore, all releases will be allocated equally in determining conformance to the design obj ectives of 10CFR50, Appendix 1.

~j The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1.

Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM; 2.

Limitation on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to Appendix B to 10CFR20.1 - 20.601, Table II, Column 2; i

3.

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10CFR20.1302 and with the methodology and parameters in the ODCM:

}

j 4.

Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents releaseo from esch unit to unrestricted areas, l

conforming to 10CFR50, Appendix I; jL 5.

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least monthly; j

6.

Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of 4

l radioactivity when the projected doses in a period of one month from the liquid effluent releases would exceed 0.12 arem to the total body or 0.4 mrem to any organ; or from the gaseous effluent releasec would exceed 0.4 mrad for gamma air dose. 0.8 mrad for.

[

beta air dose, or 0.6 mrem organ dose; 1

TS.6.5-7 7.

Limitations on the dose rate resulting from radioactive material j

released in gaseous effluents to areas beyond the site boundary conforming to the dose associated with Appendix B to 10CFR20.1 -

20.601, Table II, Column 1; 8.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10CFR50, Appendix I; 9.

Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10CFR50, Appendix I; and

10. Limitation on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40CFR190.

I.

Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the wasto gas holdup system, the quantity of radioactivity contained in gas storage tanks, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The program shall include:

1.

The limits for concentration of oxygen in the waste gas holdup system and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria; 2.

A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank is less than or equal to 78,000 curies of noble gases (considered as dose equivalent Xe-133); and 3.

A surveillance program to ensure that the quantity of radioactivity contained in each of the following tanks shall be limited to 10 curies, excluding tritium and dissolved or entrafmed noble gases:

Condensate storage tanks outside temporary tan'ks 4.

The provisions of TS 4.0 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

TS.6.7-5 C.

Environmental Reports The reports listed below shall be submitted to the Administrator of the appropriate Regional NRC Office or his designate:

1.

Annual Radiolorical Environmental Monitoring Report The Annual Radiological Environmental Monitoring Report covering the operation of the plant during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting peried. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10CFR50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiation Environmental Monitoring Reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensees participation in the Interlaboratory Comparison Program defined in the ODCM.

2.

Deleted 3.

Other Environmental Reports (non-radiological. non-souatic)

Written reports for the following items shall be submitted to the appropriate NRC Regional Administrator:

a. Environmental events that indicate or could result in a significant environmental impact casually related to plant operation. The following are examples: excessive bird impaction; onsite plant or animal disease outbreaks; unusual mortality of any species protected by the Endangered Species Act of 1973; or increase in nuisance organisms or conditions.

This report shall be submitted within 30 days of the event and shall (a) describe, analyze, and evaluate the event, including extent and magnitude of the impact and plant operating characteristics, (b) describe the probable cause of the event, (c) indicate the action taken to correct the reported event, (d) indicate the corrective action taken to preclude repetition I

I

l

{

TS.6.7-6 l

of the event and to prevent similar occurrences involving 1

similar components or systems, and (e) indicate the agencies notified and their preliminary responses.

b. Proposed changes, test or experiments which may result in a significant increase in any adverse environmental impact which l'

j was not previously reviewed or evaluated in the Final Environmental Statement or supplements thereto. This report i

shall include an evaluation of the environmental impact of the proposed activity and shall be submitted 30 days prior to 3

implementing the proposed change, test or experiment.

l i

D.

Special Reports I

Unless otherwise indicated, special reports required by the Technical Specifications shall be submitted to the appropriate NRC Regional i

j Administrator within the time period specified for each report.

4 i

4 s

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h

.