ML20211N583

Amend 4 to License NPF-36,revising Tech Specs to Eliminate Need for Performing Monthly Sampling & Analysis for Dissolved & Entrained Gases If No Waste Batch of Liquid Effluents Released During Month

ML20211N583
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	12/09/1986
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20211N581	List: ML20211N574 ML20211N583 ML20211N592
References
NUDOCS 8612180259
Download: ML20211N583 (8)

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[k 'o UNITED STATES

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LONG ISLAND LIGHTING COMPANY DOCKET NO. 50-322 SHOREHAM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 4 License No. NPF-36

1. The Nuclear Regulatory Consnission (the Commission) has found that A. The application for amendment by Long Island Lighting Company (the licensee), dated January 20, 1986, 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 endancerino the health 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.

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. NPF-36 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 4 are hereby incorporated into this license.

Long Island Lighting Company shall cperate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 9, 1986 P PD#4/PM[ OGC PD#4/D RLo:lbuld Pes.44 WButler

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3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION L

Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 9, 1986 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 4 FACILITY OPERATING LICENSE NO. NPF-36 v DOCKET NO. 50-322

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l Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf page(s) provided to maintain document completeness.*

1 Remove Insert 3/4 11-1 3/4 11-1*

3/4 11-2 3/4 11-2 3/4 12-5 3/4 12-5 3/4 12-6 3/4 12-6*

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3/4.11 RADI0 ACTIVE EFFLUENTS 7ss 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.1.3-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 4 microcurie /mL total activity.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the con-centration to within the above limits.

SURVEILLANCE REQUIREMENTS m

U 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11.1.1.1-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accord-ance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.

f SHOREHAM - UNIT 1 3/4 11-1

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TABLE 4.11.1.1.1-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum Type of of Detection Liquid Release Sampling Analysis Activity (LLD)

Type Frequency Frequency Analysis (pCi/mL)*

A. Batch Waste P ~7 P

Principa} Gamma 5x10 ReleaseTagks Each Batch Each Batch Emitters and Sumps

1. Discharge I-131 -6 1x10 Waste Sample Tanks P* M* Dissolved and -5 \

1x10 One Batch /M Entrained Gases

2. Recovery (Gamma Emitters)

Sample Tanks P M H-3 -5 d

1x10

3. Reactor Each Batch Composite u d -7 9p Gross Alpha 1x10 Drain Tank

4. Yard Pip ing Drain P Sr-89, Sr-90 5x10

-8 Q d Sump Each Batch Composite Fe-55 -6 1x10

-7 B.Continuogs D W d PrincipagGamma 5x10 Releases Grab Sample Composite Emitters

1. RHR Heat -6 Exchanger I-131 1x10 Service Water M Dissolved and -5 M 1x10 Outlet Grab Sample Entrained Gases (Gamma Emitters)

2. Reactor Building Salt Water H-3 -5 D M d

1x10 Drain Tank Grab Sample Coaposite _

Gross Alpha 1x10 0 Sr-89, Sr-90 -8 Q 5x10 d

Grab Sample Composite

-6 Fe-55 1x10

• If a batch is released during the month. l SHOREHAM - UNIT 1 3/4 11-2 Auendment I!o: 4  !

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TABLE 3.12.1-1 (Continued)

$ RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A

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EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY j AND/0R SAMPLE SAMPLES AND SAMPLE LOCATIONS" COLLECTION FREQUEN".Y OF ANALYSIS h

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4. INGESTION Z a. Milk Samples from milking animals in Semimonthly when Gamma isotopic' and I-131 location, Ial, within 5 km distance animals are on analysis semimonthly when having the highest dose potential. pasture, monthly at animals are on pasture; If there are none, then, 1 sample other times. monthly at other times.

from milking animals in each of 3 areas, Ial, between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr, or if there are none available within8km,thenalocatiog8to 17 km distant will be used.

1:' I sample from milking animals at a

• control location, Ia2, 15-30 km M distant, and not in a direction J, -prevalently downwind from the Plant.

b. Fish and 1 sample of each commercially and Sample ia season Gamma isotepic analysis' Invertebrates recreationally important species in or semiannually on edible portions.

vicinity of plant discharge area, if they are not Ib1 - Ib2. seasonal.

I sample of same species in areas not influenced by plant discharge, Ib3.

c. Food Products Samples of 3 different kinds of broad At time of harvest.I Gamma isotopic' and I-131

> leaf vegetation grown nearest each of analysis.

2 two different offsite locations of a highest predicted annual average B ground-level D/Q, if milk sampling is

% not performed, Ic1 - Ic3.

5 1 sample of each of the similar broad At time of harvest. Gamma isotopic

• and I-131 leaf vegetation grown 15-30 km distant analysis.

in the least prevalent wind direction if milk sampling is not perform, Ic3.

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TABLE 3.12.1-1 (Continued)

TABLE NOTATIONS a

5 ecific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, are provided for each and every sample location in Table 3.12.1-1 in a table and figure in the ODCM.

Refer 'a NUREG-0133, " Preparation of Radiological Effluent Technical Specifi-cations ir Nuclear Power Plants," October 1978, and to Radiological Assessment Branch '.eehnical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtain-able due to sampling equipment malfunction, every effort shall be mede to com-plete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radio-logical Environmental Operating Report pursuant to Specification 6.9.1.6. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.

In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Pursuant to Specification 6.9.1.7, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

b 0ne or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

c The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.

d Airborne particulate sample filters shall be analyzed for gross beta radio-activity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

' Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

O SH0REHAM - UNIT 1 3/4 12-6

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