ML20213D497

Amend 3 to License NPF-36,correcting Internal Inconsistency in Tech Specs Re Process Control Program for Radwaste Shipping Containers & Solidification Agents

ML20213D497
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	11/03/1986
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20213D493	List: ML20213D489 ML20213D497 ML20213D500
References
NUDOCS 8611120123
Download: ML20213D497 (8)

Text

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M UNITED STATES

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LONG ISLAND LIGHTING COMPANY DOCKET NO. 50-322

!1 SHOREHAT E ETAT PU KR"TTATION AMENDMENT TO FACILITY OPERATING LICENSE i

. Amendment-No. 3 License No. NPF-36

1. The Nuclear Regulatory Commission (the Connission) has found that A. The application for amendment by Long Island Lighting Company (the licensee), dated June 26. 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

1 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 (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 Connission's regulations; D. The issuance of this amendment will not be inimical to the common 4 i defense and security or to the health and safety of the public; and 4

E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Connission'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 i through Amendmen: No. 3 are hereby incorporated into this license.

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

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

FOR THE NUCLEAR REGULATORY COMMISSION OMWnelslyses W Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: isovember 3,1986

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

FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: November 3,1986 l

l

4 ATTACHMENT TO LICENSE AMENDMENT NO. 3 t

FACILITY OPERATING LICENSE NO. NPF-36 DOCKET NO. 50-322 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 pages provided to maintain document completeness.*

Remove Insert 6-7 6-7*

6e8 6-8 6-17 6-17 6-18 6-18*

1

ADMINISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for the station staff shall be maintained u'ider the direction of the Training Supervisor, shall meet or exceed the requirements and recommendations of Section 5 of ANSI 18.1-1971 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational expcrience identified by the ISEG.

6.5 REVIEW AND AUDIT 6.5.1 REVIEW OF OPERATIONS COMMITTEE (ROC)

FUNCTION 6.5.1.1 The ROC shall function to advise the Plant Manager on all matters

, related to nuclear safety.

COMPOSITION

6. 5.1. 2 The ROC shall be composed of the:

Chairman: Opt: rations Manager

' Alternate Chairman: Plant Manager Alternate Chairman and member: Maintenance Manager Member: Operating Engineer Member: Maintenance Engineer Member:

Instrument and Control Engineer g,o Member: Reactor Engineer Hember: Health Physics Engineer Member:

Radiological Controls Manager ALTERNATES

6. 5.1. 3 All alternate members shall be appointed in writing by the ROC Chair-man; however, no more than two alternates shall participate as voting members l in ROC activities at any one time.

I MEETING FREQUENCY

6. 5.1. 4 The ROC shall meet at least once per calendar month and as convened by the ROC Chairman or his designated alternate.

QUORUM

6. 5.1. 5 The quorum of the ROC necessary for the performance of the ROC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four other members including alternates.

SHOREHAM - UNIT 1 6-7 e,.-...-....--- , _

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-.m-ADNINISTRATIVE CONTROLS RESPONSIBILITIES 6.5.1.6 The ROC shall be responsible for:

a.

Review of (1) all proposed procedures required by Specification 6.8 and changes thereto, (2) all proposed programs required by Specifi-cation 6.8 and changes thereto, and (3) any other proposed procedures or changes nuclear thereto as determined by the Plant Manager to affect safety; b.

Review of all proposed tests and experiments that affect nuclear safety; c.

Review of all proposed changes to Appendix A Technical Specifications; d.

Review of.all proposed changes or rodifications to unit systems or ~

equipment that affect nuclear safety; e.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering eva,lu- ,

ation and recommendations to prevent recurrence, to the Vice President-Nuclear Operations and to the Nuclear Review Board;

f. Review of.all REPORTABLE EVENTS; g.

Review of station operations to detect potential hazards to nuclear safety; h.

Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant Manager or the Nuclear Review Board; NNdd"A 1.

Review of the Security Plan and implen,enting procedures and submittal "~

of recommended changes to the Nuclear Review Board;  !

j. *

? Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Nuclear Review Board;

k. q Review of the proposed changes to the Process Control Program (PCP);  ;

1.

Review (ODCM); of the proposed changes to the Offsite Dose Calculation Manual j'

, s.

Review of the proposed Major Changes to Radioactive Waste Systems;

n. f Review of Personnel Radiation Records annually to determine,how expos-ures might be lowered consistent with ALARA principles. Document such considerations; and a 3

c.

Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President- . . _

Nuclear Operations and to the Nuclear Review Board.

6.5.1.7 The ROC shall:

a.

. Recommend in writing to the Plant Manager approval or disapproval of items considered under Specification 6.5.1.6a. through d. and m.

prior to their implementation, l b.

Render determinations in writing with regard to whether or not each ites considered under Specification 6.5.1.6a. through e. above constitutes an unreviewed safety question.

SHOREHAM - UNIT 1 6-8 Amendment No. 3

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ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued)

(Figure 5.1.3-1) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accord- l ance with the methodology and parameters in the 0FFSITE D0SE CALCULATION MANUAL (0DCM). 1 The Semiannual Radioactive Effluent Release Report to be submitted 60 days after '

January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent path-ways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977. ,

The Semiannual Radioactive Effluents Release Reports shall include the following information for each type of solid waste (as defined by 10 CFR Part ~61) shipped i offsite during the report period:

a. Container volume, a

b. Total curie quantity (specify whether determined by measurement or estimate),

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l c. Principal radionuclides (specify whether detemined by measurement p or estimate),

M k~ d. Source of waste and processing employed (e.g., dowatered spent resin, F compacted dry waste, evaporator bottoms),

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Type of container (e.g., LSA box, HIC, steel liner, 55 gallon drum),

and

f. Solidification agent (e.g., cement, bitumen, Dow media). l l

The Semiannual Radioactive Effluent Release Reports shall include a list and '

description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period.

The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new loca-tions for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

SH0RENAM - UNIT 1 6-17 Amendment No. 3

, ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the main steam system safety- -

rolief valves, shall be submitted on a monthly basis to the Director, Office of R:s urce Management, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy to the Regional Administrator of the Regional Offics of the

-NRC no Icter than the 15th of each month following the calendar month covered by th? report.

SPECIAL REPORTS i

,6.9.2 Special reports shall be submitted to the Regional Administrator of the R;gional Office of the NRC within the time period specified for each report. 'plr

!!'i 6.10 RECORD RETENTION h*

'6.10.1 In addition to the applicable record retention requirements of Title

]f 10 Cod 2 of Federal Regulations, the following records shall be retained for

, at Icast the minimum period indicated. _ lfl S

^

6.10.2 The following records shall be retained for at least 5 years: dli!ipuliL,.,.,. m

~. 9

a. Records and logs of station operation covering time interval at each j '" ' -

power level. i

b. Records and l'ogs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to TP nuclear safety.

4

c. All REPORTABLE EVENTS.

d. Records of surveillance activities, inspections, and calibrations i required by these Technical Specifications.

o. Records of changes made to the procedures required by Specification M

"'j 6.8.1.

f. Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material of record.

6.10.3 The following records shall be retained for the duration of the unit Oper; ting License:

a. Records and drawing changes reflecting station design modifications made to systems and equipment described in the Final Safety Analysis Report.

.SHOREHAM - UNIT 1 6-18