Text

Amend 127 to License DPR-59,clarifying & Correcting Minor Problems & Errors in Radiological Environ Tech Specs & Reporting Requirements for Major Mod to Radwaste Sys
	ML20247D798
Person / Time
Site:	FitzPatrick
Issue date:	05/09/1989
From:	Capra R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20247D804	List: ML20247D798; ML20247D837;
References
	NUDOCS 8905260007
	Download: ML20247D798 (19)
	v • d • e

_ _ _ _ _ _ _ _ _ _ _

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NUCLEAR REGULATORY COMMISSION h

j WASHINGTON, D. C. 20555 pl POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.127 License No. DPR-59 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Power Authority of the State of New York (the licensee) dated May 19, 1988, 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 (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the 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 a;cordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follrws:

8905260007 890509 DR ADOCK 0500 3

2 (2) Technical Specifications

~

The Technical Specifications contained in Appendices A and B, as revised through Amendment No.127, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

l l

3.

This license amendment is effective as of the date of its issuance J

to be implemented within 30 days.

)

FOR THE NUCLEAR REGULATORY COMMISSION S N CL. Cw -

Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects, I/II

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 9, 1989 Ib

4 ATTACHMENT TO LICENSE AMENDMENT NO.127 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET-NO. 50-333 Revise Appendix A as follows:

O Remove Pages Insert Pages Appendix B:

5 5

'21 21 23 23

' 28.

28 30 30 31 31

'33' 33 37 37

'38 38 49 49 l

56 56 l

58 '-

58 59 59 60 60 68 68 Appendix A: 258c-258c

Tabis 2.1-1 i

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Ooerable Action Gross radioactivity monitors providing alarm and automatic termination of release Liquid radwaste effluent line 1

(a) l Gross beta or gamma radioactivity monitors providing alarm but not providinn automatic termination of release Service water system effluent line 1

(b)

Flow rate measurement devices Liquid radwaste effluent line 1

(c)

NOTES FOR TABLE 2.1-1 1

(a) With the number of operable channels less than the required minimum number, effluent releases may continue provided that prior to initiating a releases

a. Two independent samples are analyzed; l

b. Two technically qualified members of the facility staff verify the discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

(b) With the number operable of channele less than the required minimum number, effluent releases in this pathway may continue provided that, i

at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analysed i

for principal gamna emitters at a limit of detection of at least 5x10-7 microcuries/ml.

The principal gamma emitters for which the LLD specification applies exclusively are described in Note (c) to Table 2.2-1.

(c) With the number of operable channels less than the required minimum number, effluent releases via this pathway may continue provided the flow rate is estimated at least once per four hours during actual releases.

Pump curves or tank level decreases generated in situ may l

be used to estimate flow.

1 l

Amendment No. %

127 l

l I

TABLE 3.3-l' 4

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM l

Lower Limit of Detection Minimum

' Gaseous Release Sampling Analysis Type of Activity (LLD)(a)

Type Frequency Frecuency Analysis fuC1/ml)

Main Stack and Monthly Monthly Principal Gamma 1 x 10 ' Refuel Floor Vent Grab Noble' Emitters (D) and S ample (d)

Gases (D)

Reactor Building Vent and Quarterly Quarterly H-3 1 x 10-6 Turbine Building Grab Sample Vent and Radwaste Building Continuous (c)

Weekly I-131 1 x 10-12 Vent Charcoal Sample (*)

I-133 None l

Continuous (c)

Weekly Principal Gamma 1 x 10-11' Particulate Emitters (b)

Sample (*)

(I-131, I-133, others)

None l

Continuous (c) 1 Wk/Mo Gross Alpha 1 x 10-11 Particulate Sample Continuous (c) 4 Wk/Qr Sr-89, Sr-90 1 x 10-11 Composite Particulate S ample Continuous (c)

Noble Gas Noble Gases 1 x 10-5 Monitor Gross Beta or Gamma Incinerated Prior Each Principal Gamma 5 x 10-7 Oil (f) to Each Batch (9)

Emitters (b) l Batch (9)

I-131 1 x 10-6 l

Amendment No. po 127

NOTES FOR TABLE 3.2-1 (continusd)

(d)

' Main stack gaseous sampling and analysis shall also be performed following shutdown, startup, or a thermal power change exceeding 20% of rated thermal power in one hour.

1.

This requirement applies only ift o

Analysis shows that the dose equivalent I-131 concentration in the primary coolant has increased more than a factor of 3; and o

The noble gas monitor shows that effluent activity has increased

.more *.han a factor of 3; and o

Corrections for increases due to changes in thermal power level have been made in both cases.

(e)

Main stack iodine. and particulate sampling shall also be performed daily.

following each shutdown, startup or thermal power change exceeding 20% of rated thermal power in'one hour.

1.

Daily sampling is not required for thermal power changes if the off gas charcoal filters are in service.

2.

In addition, this requirement applies only ift o

Analysis shows that the dose equivalent I-131 concentration in the primary coolant has increased more than a factor of 3; and o

The noble gas monitor shows that effluent activity has increased more than a factor of 3; and o

Corrections for increases due to changes in thermal power level have been made in both cases.

3.

Daily sampling shall be performed until two consecutive samples show no increase in concentration but not to exceed 7 consecutive days.

4.

LLDs may be increased by a factor of 10 for analysis of daily samples.

5.

Analysis of daily and weekly samples shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing.

(f)

Incinerated oil may be discharged via points other than the main stack and l

building vents (i.e.,

auxiliary boiler).

Whenever oil samples cannot be filtered such as No. 6 bunker fuel oil, raw oil samples shall be collected and analyzed.

(g)

Samples of incinerated oil releases shall be collected f rom and representative l

of filtered oil in liquid form.

Whenever oil samples cannot be filtered such as No. 6 bunker fuel oil, raw oils samples shall be collected and analyzed.

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NOTES TO FIGURE 5.1-1 (a)

NKP1 stack (height is 350 feet)

(b) NMP2 stack (height is 430 feet)

(c) JAFNPP stack (height is 385 feet)

(d) Building vents (e) NKP1 radioactive liquid discharge (Lake Ontario, bottom)

(f) NMP2' radioactive liquid discharge (Lake Ontario, bottom)

(g) JAFNPP radioactive liquid discharge (Lake Ontario, bottom)

(h)

Site boundary (i) Lake Ontario shoreline Additional Information:

NNP2 reactor building vent is located 187 feet above ground level JAFNPP. reactor and turbine building vents are located 173 feet above ground level JAFNPP radwaste building vent is 112 feet above ground level i

Amendment No. # 127 49 L.

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.a NOTES FOR TABLE 6.1-3 (a) The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability and with 5%

j probability of falsely concluding that a

blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation),

4.66 sb LLD =

E*V* 2.22

Y

exp (- S t)

Where:

LLD is the a orlori lower limit of detection, as defined above (in picocurie per unit mass or volume);

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (in counts per minute);

E is the counting efficiency (in counts per transformation);

V is the sample size (in units of mass or volume);

2.22 is the number of transformations per minute per picoeuries Y is the-fractional radiochemical yield (when applicable);

Ais the radioactive decay constant for the particular radionuclides; At is the elapsed time between sample collection (or end of the sample collection period) and time of counting.

Typical values of E,

V, Y,

and At should be used in the calculations.

(b)

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.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine con-ditions.

Occasionally background fluctuations, unavoidable small sample sises, the presence of interfering nuclides, or other uncon-tro11able circumstances may render these LLDs unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

(c) No drinking water pathway exists at the Nine Mile Point Sito under normal operating conditions due to the direction and distance of the' nearest drinking ' water intake.

Therefore, an LLD value of 15 pCi/ liter is used.

Amendment No. jHI 127 60 l

7.

The Radioactive Effluent Release Report shall contain the cause for unavailability of any environmental - sample required by Table 6.1.1 and shall identify the locations for obtaining replacement samples.

This shall also include a revised figure (s) and table for the ODCM reflecting the new location (s).

Refer to Specification 6.1.c.

8.

The Radioactive Effluent Release Report shall contain new locations identified in the land use census in accordance with Specifications 6.2.b or 6.2.c.

9.

The Radioactive Effluent Release Report shall contain the events leading to the condition which resulted in exceeding 10 curies for tanks specified in the Limiting Conditions for Operation, Section 2.5.a.

d.

Annual Radioloolcal Environmental Doeratina Report Routine Radiological Environmental Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental ' surveillance activities for the report period.

The report shall include a

comparison with preoperational

studies, operational controls (as appropriate), and environmental surveillance reports from the previous five years, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of the Land Use Census required by Specification 6.2 The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiologicci environmental samples and of all measurements taken during the period pursuant to Table 6.1-1, as well as summarized and tabulated results of those analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.

In the event that some individual results are not available for inclusion in the report, the report shall note and explain 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; at least two legible maps

covering all sampling locations and keyed to a table giving distances and directions from the centerline of one reactor; the results of participation [

in the Interlaboratory Comparison Program required by Specification 6.3 (or appropriate EPA cross-check program code), and discussion of all analyses in which the LLD's required by Table 6.1-3 were not routinely achievable.

One map shall cover stations near the site boundary; a second shall include l

the more distant stations.

Amendment No. f[

127 I

68 i

)

I

)

J C.-

Revisions of the ODCM:'

1.

shall be submitted to the Commission in the Semlannual Radioactive Effluent Release Report for the period in which the revisions were made effective. This submittal shall contains

a. sufficiently detailed information to support. the rationale for the revisions without benefit of additional information (information submitted shall consist of revised pages of the ODCM, with each page numbered and provided with an approval and date

box, together with appropriate evaluations justifying the revisions);

b. a determination that the revisions will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and

c. documentation - that the revisions have been reviewed and found acceptable by the PORC.

2.

shall become effective upon issue following review and acceptance by the PORC.

6.18 MAJOR MODIFICATIONS TO RADIOACTIVE LIOUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS

A.

Major modifications to radioactive waste systems (liquid, gaseous and solid):

1.

shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the modification is completed and made operational.

The discussion of each modification sha11'contains a.

a summary of the evaluation that led to the determination that the modification could be made in accordance with 10 CFR 50.59; b.

sufficient information to support the reason. for the modification without benefit of additional or supplemental information and c.

a description of the equipment, components and processes involved and the interf aces with other plant systems.

The Authority may elect to submit the information called for in this Specification as part of the annual 10 CFR 50.59 Safety ' Evaluation Report.

Amendment No. g 127 258c

ML20247D798

Text

Attachment:

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