ML20064L250

Proposed Tech Specs Re Nonradiological Specs in App B

ML20064L250
Person / Time
Site:	FitzPatrick
Issue date:	02/10/1983
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20064L236	List: ML20064L233 ML20064L243 ML20064L250
References
NUDOCS 8302150166
Download: ML20064L250 (13)

Text

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ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO NON-RADIOLOGICAL SPECIFICATIONS IN APPENDIX B POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO 50-333 DPR-59 8302150166 830210 PDR ADOCK 05000333 P PDR

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CONTENTS Page 1.0 Definitions ........................................... 1 2.0 Protection Limits ...................................... 2 2.1 (Deleted) 2.2 (Deleted) 9 2.3 Radioactive Discharge ............................. 6 3.0 (Deleted) 4.0 Environmental Surveillance and Special Study Programs . 33 4.1 (Deleted) 4.2 (Deleted) 4.3 Environmental Radiological Monitoring .......,...... 33 Amenement No. 4 i

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LIST OF TABLES Page 4.3-1 Sample Collection and Analysis NMP-JAF Site Radiological Environmental Monitoring Program ... 34 Amendment No. [ iii l

List of Figures Page 5.2-1 Plant Organization - Environmental .......... 43 5.2-2 Management Organization - Environmental ..... 44 Amendment No. iv

1 1.0 Definitions Normal Plant Operation is with the reactor critical and above one percent rated power and in conformance with the re-quirements of the Technical Specifications.

Sample. Material gathere4 such as water or fish, for the purpose of analyzing for a certain parameter or characteristic.

Sub-sample. A sample which is divided in a uniform manner so as to make the analysis of the smaller portion representative of the total sample. For example, a large sample of fish would be divided into a smaller sample with the same ratio of species and weight of fish as the whole sample.

Amendment No.

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1 d d e e t t e e l l S e e N d d O y y I

2 T l l A l l R a a E n n P o o O i i t t R n n O s e e F t t t i n n S m i i N i O L n n I o o T n i i I o t t D i c c o N t e e N O c s s C e t t s s n G o i i e

N r h h I P T T m T d I n e

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Pages 3 -5 Intentionally deleted.

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Amendment No. , 3

Pages 16a -32 Intentionally deleted.

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Amendment No. 16a

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4.0 Environmental Surveil' lance and Special Study Programs 4.1 (Deleted) 4.2 (Deleted) 4.3 Environmental' Radiological Monitoring OBJECTIVE An environmental radiological monitoring program shall be conducted to evaluate the effects of station operation on the environs and to verify the effectiveness of the controls on radioactive materials sources.

SPECIFICATION An environmental radiological monitoring program shall be conducted as follows:

I 1. The environmental radiation monitoring program specified in Table 4.3-1 shall be conducted.

2. Reporting requirements for the environmental radiological monitoring program are outlined in Sect. 5.5, Plant Reporting Requirements. 1

3. During the seasons that animals producing milk for human consumption are on pasture, samples of fresh milk shall be obtained from these animals at the frequencies and number of locations shown in Table 4.3-1 and analyzed for their radioiodine content, calculated as I-131. Analysis shall be carried out within eight days (one I-131 half-life) of sampling. Suitable analytical procedures shall be used to determine the radioiodine concentration to a sensitivity of 0.5 picocuries per liter of milk at the time of sampling. .For activity levels at or above 0.5 picocuries per litor, overall error (one sigma confidence level) of the analysis shall be within + 25 percent. Results l shall be reported, with associated calculated error, as picocuries of I-131 per liter of milk at the time of sampling.

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Amendment No. 33

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b. Ra'dioactive Ef fluent Release T.eport A report on the radioactive discharges released from the sito during the previous 6 months of operation shall be submitted to the Director of the NRC Regional Of fice (with a copy to the Director, Of fice of Nuclear Raac:or Regulation) within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial s== mary of the quan-criticality. The report shall include a tities of radioactive liquid and gaseous effluents and solid waste released f rom the plant as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Ef fluents from Light-Water-Cooled Nuclear Power Plants ," with data su=marized on a quarterly basis following the format of Appendix B thereof.

The report .shall include a summary of the meteorolo-gical conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, with data su==aficed on a quarterly basis following the format of Appendix B thereof.

5.G.2 Nonroutine Reports

a. Nonroutine Environmental Operating Reports _

A report shall be submitted in the event that (a) a limiting condition for operation is exceeded (as specified in Section 2, " Limiting Conditions for-operation")or(b)an unusua'l "impo'rtant event occurs that causes a tignificant environmental impact.

(1) Prompt Report. Those events requiring prompt reports shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone , tele-graph, or facsimile transmission to the Director of the NRC Regional Office and within 14 days by a written report to the Director of the Ragional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) .

(2) 30-Cay Report. These events not . requiring prompt reports shall be reported within 30 days by a written report to the Director of the NRC Regional Of fice (with a copy to the Director, Of fice of Nuclear Reactor Regulatioh) .

(Written 14-day and 30-day reports .and, to the extent possible, the preliminary telephone, telegraph, or facsimile reports shall (a) describe, analyze, and evaluate the occurrence, including extent and magnitude of the impact, (b) describe the cauce o f the occurrence , and (c) indicate the correcti-ve' action (including any significant changes made in procedures) taken to preclude repetition of the accurrence and to prevent similar occurrences in'vciving similar cc=ponents or systems.

Acendment No. - 4o

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! 5.5.2 Plant Operating Procedures include provisions, in addition to the procedures specified in Section 5.5.1, to ensure that all plant systems and components are operated in compliance with the limiting conditions for operations established as part of the Environmental Technical Specifications.

5.6 PLANT REPORTING REQUIREMENTS

[ 5.6.1 Routine Reports t

I a. Annual Environmental Operating Report (This part intentionally deleted. )

A report on the radioloqical environmental surveillance programs for the previous 12 months of operation shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document within 90 days after January 1 of each year. The period of the first report shall begin with the date of initial criticality. The reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by the Technical Specifications. If harmful effects or evidence of irreversible damage are detected by the monitoring, thi licensee shall provide an analysis of the problem and a preposed course of action to alleviate the problem.

Results of all radiological environmental samples taken shall be summarized and tabulated on an annual basis. In the' event that some results are not available within the 90 day period, 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 supp?amentary report.

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j Amendment No, y$,pd 39 1

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ATTACHMENT II SAFETY EVALUATION RELATED TO NON-RADIOLOGICAL SPECIFICATIONS IN APPENDIX B l

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a POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO 50-333 DPR-59 1

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SECTION I - DESCRIPTION OF THE Ci1ANGES The proposed changes delete all non-radiological specification sections and references from Appendix B. In the table of contents (page i), all of Section 3 is deleted, and Subsections 2.1, 2.2, and 4.1 are deleted. Section 4.0, " Environmental Surveillance and Special Study Programs," begins on page 33 rather than page 20.

Tables 2.2-2, 4.1.1-1 and 4.1.1-2 are deleted from the List of Tables on page iii. Figure 4.1.1-1 is deleted from the List of Figures on page iv.

The " Ambient Lake Temperature" definition is dsleted from Section 1.0, page 1.

Subsection 2.1, " Thermal," is deleted from Section 2,

" Protection Limits," on page 2. Pages 3 through 5, covering all of Subsections 2.1 and 2.2 (Thermal Limits and Chemical Limits), are deleted.

Pacas 16a through 32, covering all of Section 3 (" Design and Operating Practices") and Subsection 4.1 ("Eiological"), are deleted. Section 4, ' Environmental Surveillance and Special Study Programs," begins on page 33 rather than page 20. Subsection 4.2 was deleted in a previous Technical Specification change approved by the Commission.

In Subesction 5.6.2a (pags 40), "Nonroutino Environmsntal Operating Reports," part (b) in the first paragraph, referencing Section 3, is deleted. Part (c) in the same paragraph is relabeled as part (b).

In Subsection 5.6.la on page 39, " Annual Environmental Operating Report," the non-radiological reporting requirements (Part A) are deleted.

SECTION II - PURPOSE OF THE CHANGES The non-radiological deletions from Appendix B are being proposed at the request of the Nuclear Regulatory Commission as a ministerial action prescribed by law (the Federal Water Pollution Act Amendments of 1972). Hanceforth, non-radiological environmental regulatory requirements will be applied and enforced under the FitzPatrick pollution discharge permit granted by New York Stato.

As amended, Appendix B will reflect the Nuclear Regulatory Commission's jurisdiction only over radiological environmental regulations.

SECTION III - IMPLEMENTATION OF THE CHANGES The changes, as proposed, will not adversely impact the ALARA or Fire Protection programs at FitzPatrick.

- Moreover, the changas'will not advernoly impact tha environment. Henceforth, non-radiological environmental regulatory requirements will be applied and enforced under the FitzPatrick pollution discharge permit granted by New York State.

SECTION IV - CONCLUSION The incorporation of these changes: a) will not increase the probability or the consequences of an accident or malfunction of equipment important to safety as previcusly evaluated in the Safety Analysis Report; b) will not increase the possibility of an accident or malfunction of a type other than that evaluated previously in the Safety Analysis Report; c) will not reduce the margin of safety as defined in the basis for any technical specification; and d) does not constitute an unreviewed safety question.

SECTION V - REFERENCES i

1. James A. FitzPatrick Facility Operating License, Appendix B (Environmental Technical Specifications.'.

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