ML20030D008
| ML20030D008 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 08/26/1981 |
| From: | Mccaffrey B LONG ISLAND LIGHTING CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| SNRC-616, NUDOCS 8108310270 | |
| Download: ML20030D008 (22) | |
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LONG ISLAND LIGHTING COM PANY fi t*O -
SHOREHAM NUCLEAR POWER STATION w
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P.O. BOX 618, NORTH COUNTRY ROAD + WAQtNG RIVER, N.Y.11792
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August 26, 1981 SNRC-616 Mr. Harold R.
Denton, Director Office of Nuclear Reactor Regulatior.
U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Shoreham Nuclear Power Station-Unit 1 Docket No. 50-322
Dear Mr. Denton:
Enclosed herevith are fifteen (15) copies of a document pre-pared by the Long Island Lighting Company entitled " Compliance of Shoreham Nuclear Power Station - Unit 1 with the NRC Regu-lations of 10CFR Parts 20, 50, and 100".
This document ad-dresses those sections of the regulations which impose require-ments on Ghoreham, l
If you require additional information, please do not hesitate to contact this office.
Very truly yours,
/$/L ?Z' Y B.
R. McCaf rey l
Manager, Proj Engineering Shoreham Nuclear Power Station cc,pg Obf Enc.
cc:
J.
Higgins
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//I 0108310270 810826 PDR ADOCK 05000322 A
Summary of Compliance with the Code of Federal Regulations Titic 10 - Energy Chapter I - Nuclear Regulatory Commission Parts 20, 50 and 100 January 1, 1981 for Shoreham Nuclear Power Station - Unit 1 Long Island Lighting Company
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Introduction This document presents a summary of the compliance of the
, y Shoreham Nuclear Power Station - Unit I (SNPS) design and operation to the NRC regulations put forth in 10 CFR Parts 20, 50 and 100.
Those sections of the regulations which are appli-cable to Shoreham and impose requirements on applicants for and holCers of Operating Licenses are addressed.
Regulations per-taining to Construction Permits are not discussed.
L
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ENCLOSURE COMPLIANCE OF SHOREHAM NUCLEAR POWER STATION UNIT 1 WITH THE NRC REGULATIONS OF 10CFR PARTS 20, 50, and 100 Regulation (10CFR)
Compliance 20.1 (c)
Conformance to the ALARA principle stated in this regulation is ensured by implemen-tation of the management pclicy stated in Section 12.1.1.1 of the FSAR.
This imple-mentation encompasses appropriate Technical Specifications, Health Physics procedures, delegation of responsibility and an on-going training program.
Chapters 11 and 12 of the FSAR describe the specific equipment and design features utilized in this effort.
20.3 The definitions contained in this regula-tion are adhered to in applicable sections of the FSAR and all appropriate Technical Specifications-and procedures.
20.4 The Units of Radiation Dose specified in this regulation are all applicable SNPS procedures.
20.5 The Units of Radioactivity specified in this regulation are used in all applicable SNPS procedures.
20.101 The radiation dose limits specified in this regulation are complied with through the implementation of and adherence to adminis-trative policies and controls, and in appropriate Health Physics procedures developed for this purpose.
Conformance is documented by the use of appropriate personnel monitoring devices and the main-tenance of all required records (See FSAR Chapter 12).
20.102 When required by this regulation, before permitting any individual to exceed the exposure limits specified in 20.101(a) pre-vious accumulated occupational dose is determined by the use of the equivalent to 1
Regulation (10 CFR)
Compliance 20.102 (con' t. )
Form NRC-4.
Appropriate Health Physics procedures and administrative policies con-trol this process. (See FSAR Chapter 12).
20.103 (a)
Compliance with this regulation is ensured through the implementation of appropriate Health Physics procedures relating to air sampling for radioactive materials, and bioas'say of individuals to measure radio-activity Administrative policies and controls will provide adequate margins of safety for the protection of individuals to measure radioactivity in the body.
Administrative policies and controls will provide adequate margins of safety for the protection of individuals against the intake of radioactive materials.
The sys-tems and equipment described in Chapters 11 and 12 of the FSAR provide the capability to minimize these hazards.
20.103 (b) (1)
The reactor building ventilation system is designed to provide a means to reduce the concentration of particulate and gaseous contamination to assure safe continuous access (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> / week) during normal reac-tor shutdown (See FSAR Section 12.3.3i Portable ventilation systems, hoods, and tents are used as practicable to contain and reduce airborne particulate and gaseous contamination during the performance of various jobs.
20.103 (b) (2)
Compliance with this regulation is ensured through the implementation of appropriate Health Physics procedures relating
.o air sampling for radioactive materials, and bioassay of individuals for-internal con-tamination.
Administrative policies and controls will provide adequate margins of safety for the protection of individuals against the intake of radioactive mater-ials.
The systems and equipment described in Chapters 11 and 12 of the FSAR provide the capability to minimize these hazards.
2 J
l Regulation (10 CFR)
Compliance 20.103 (b) (2)
Issuance and Selection of Respiratory (Con't.)
Equipment Health Physics personnel at SNPS will so-1cct appropriate respiratory equipment so that contac2nant concentration inhaled by the wearer does not exceed the appropriate regulatory limits specified in Appendix B, Table I, Column 1. Should an individual recei've greater than 40 Maximum Permissible Concentration (MPC) hours in 7 consecutive days, an evaluation will be made to identify 1
the cause and actions will be taken to pre-vent recurrence.
Recoros will be main-tained for each occurrence.
20.103 (c)
Health Physics personnel at SNPS will so-lect appropriate respiratory equipment so that contaminant concentration inhaled by the wearer does not exceed the appropriate regulatory limits.
The protection factors used at SNPS comply with the protection factors permitted under 1
20.103 (e)
The NRC Region I Director ehn11 be notified at least 30 days before respiratory protec-l tive equipment is first used under the provisions of this section.
20.104 Conformance with this regulation is accomp-lished through the use of the appropriate Health Physics procedurcs.
Access to re-stricted areas ir minimized to assure that minors do not revo.ve a dose in excess of 10 percent of the limits specified in 20.101, paragraph (a).
20.105 (a)
This regulation allows information con-cerning anticipated average radiation levels and anticipated occupation times for each of the unrestricted areas to be submitted.
Chapters 11 and 12 of the FSAR provide the information and related dose assessments.
LILCO has not and does not currently intend to modify limits for unrestricted areas.
3
Regulation (10 CFR)
Compliance 20.105 (b)
The radiation dose rate limits specified in this regulation will be complied with through the implementation of SNPS procc-dures, Technical Specifications, and administrative policies which control the use and transfer of radioactive materials.
Appropriate surveys and monitoring devices will document this complience.
20.106 (a)
Conformance with the limits specified in j
this regulation will be assured through the implementation of SNPS procedures and applicable Technical Specifications which provide adequate sampling and analyses, ar.d monitoring of radioactive materials in effluents before and during their release.
The level of radioactivity in station ef-fluents will be minimized to the extent practicable by the use of appropriate equipment designed for this purpose, as described in Chapter 11 of the FSAR.
i 20.106 (b) & (c)
LILCO has not and does not currently intend to include in any license or amendment applications proposed limits higher than those specified in 20.106 (a), as provided in these regulations.
20.106 (d)
Appropriate allowances for dilution, dis-persion and decay of radioactive effluents will be made in conformance with this regt-lation, and are described in detail in Chapter 11 of the FSAR.
20.108 Necessary bioassay equipment and proco-dures, including Whole Body Counting, will be utilized to determine exposure of indi-viduals to concentrations of radioactive materials.
Appropriate Health Physics I
procedures and administrative policies f
implcment this requirement. (See FSAR Chapter 12.)
20.201 The surveys required by this regulation will be performed at adequate frequencies and contain such detail as to be consistent with the radiation hazard being evaluated.
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Regulation (10 CFR)
Compliance 20.201 (Con't.)
When necessary, the Radiation Work Permit program established at the station provides for detailed physical surveys of equipment, structures and work sites to detarmine appropriate levelsaof radiation protection.
The SNPS Administrative Procedures and applicable Health Physics procedures will require these surveys and provide for their documentation in such manner as to ensure compliance with the regulations of 10CFR Part 20.
(See FSAR Chapter 12.)
20.202 (a)
The applicable SUPS Health Physics proce-dures will set forth policies and practices which ensure that all individuals are supplied with, and required to use, appro-priate personnel monitoring equipmcr,t.
The Radiation Work Permit system will be estab-lished to provide additional control of personnel working in radiation areas and to ensure that the level of protection afforded to these individuals is consistent with the radiological hazards in the work place. (See FSAR Chapter 12.)
20.202 (b)
The terminology set forth in this regula-tion will be used in all applicable SNPS Health Physics procedures, Technical Speci-fications, and Administrative Procedures.
20.203 (a)
All materials used for labeling, posting, or otherwise designating radiation hazards or radioactive materials, and using the radiation symbol, conform to the conven-tional design prescribed in this regulation per SNPS Health Physics procedures.
20.203 (b)
This regulation will be conformed to, through the implementation of appropriate Health Physics procedures relating to post-l ing of radiation areas, as defined in l
20.203 (c)
The requiremeni.s of this regulation for "High Radiation Areas" will be conformed to by the implementation of the SNPS Technical Specifications and appropriate SNPS Health 5
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Regulation (10 CFR)
Compliance 20.203 (c) (Con't.) Physics procedures.
The controls and other protective measures set forth in the regu-lation are maintained under the surveil-lance of the SNPS Health Physics section.
20.203 (d)
Each Airborne Radioactivity Area, as de-fined in this regulation, will be required to be posted by provisions of the appro-priate SNPS Health Physics procedures.
1 These procedures also provide for the surveillance requirements necessary to determine airborne radioactivity levels.
20.203 (e)
The area and room posting requirements set forth in this regulation pertaining to radioactive materials will be complied with through the implamentation of appropriate SNPS Health Physics procedures.
20.203 (f)
The container labeling requirements set forth in this regulation will be complied with through the implementation of appro-prihte Health Physics procedures.
20.204 (a), (c), (d)
The posting requirement exceptions des-cribed in this regulation are used where appropriate and necessary at SNPS.
Ade-quate controls are provided within the SNPS, health physics procedures to ensure safe and proper application of these excep-tions.
20.205 The requirements of this regulation pertaining to procedures for picking up, receiving, and opening packages of radio-active materials will be implemented by the appropriate SNPS Health Physics proce-dures.
These procedures also provide for the necessary documentation to ensure an auditable record of compliance.
20.206 The requirements of 10 CFR 19.12 referred to by this regulation are satisfied by the rrdiation worker training conducted at SNPS.
Appropriate administrative prcce-dures set forth requirements for all 'radia-tion workers to raceive this instruction on a periodic basis.
(See FSAR Chapter 12.)
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l.
Regulation (10 CFR)
Compliant 3 20.207 Licensed materis]s at SNES are controlled through the Licensed Source Users Commit-tee.
If licensed materials are in unre-stricted areas they will be stored and/or controlled in accordance with this section.
20.301 The general requirements for waste disposal set forth in this regulation are complied with through SNPS Health Physics proce-dures, the Technical Specifications, and the provisions of the station operating license.
Chapter 11 of the FSAR describes the Solid Waste Disposal System installed at SNPS.
20.302 No such application for proposed disposal procedures, as described in this regula-tion, has been made or is currently contem-plated at LILCO.
20.303 No plans for waste disposal by release into sanitary sewerage systems, as provided for in this regulation, are contemplated by SNPS, nor is this practice currently util-ized.
20.304 No plans for waste disposal by burial in soil, as provided for in this regulation are contemplated by SNPS, nor is this prac-tice currently utilized.
20.305 Specific authorization, as described in this regulation, is not currently being sought by LILCO for treatment or disposal of wastes by incineration.
20.401 All of the requiremertz of this regulation will be complied with through the implemen-tation of appropriate Technical Specifica-tions and health physics procedures per-taining to records of surveys, radiation monitoring and waste dispossl.
The reten-tion periods specified for such records are also provided for in these specifications and procedures.
(See FSAR Chapter 12.)
20.402 SNPS has established an appropriate inven-tory and control program to ensure strict accountability for all licensed radioactive 7
Regulation (10 CFR)
Compliance 20.402 (Con't.)
materials.
Reports of theft or loss of licensed material will be required by refe-rence to the applicable regulations and~in the Technical Specifications.
20.403 Notifications of incidents, as described in this regulation, will be assured by the requirements of the Technical Specifica-tions, the SNPS Administrative Procedures and appropriate plant procedures, which also provide for the necessary assessments to determine the occurrence of such inci-dents.
20.405 Reports of overexposures to radiation and the occurrence of excessive levels and concentrations, as required by this regula-tion, will be provided for in the Technical Specifications and in appropriate Health Physics procedures.
20.407 The requirements of personnel monitoring reporting will be complied with and appro-priate Health Physics procedures estab-lished to generate a data base.
20.408 The report of radiation exposure required by this regulation upon termination of an individual's employment or work assignment i
is generated through the provinions of the i
Health Physics procedures.
20.409 The notification and reporting requirements of this regulation, and those referred to by it, are satisfied by the provisions of j
the Health Physics procedures.
l 50.10 An Operating License has been applied for l
in accordance with applicable regulations cnd is currently under review by the Commission.
50.30 This regulation sets forth procedural re-quirements for the filing of license appli-cations.
LILCO has complied with the pro-cedural requirements in effect at the time
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of filing its license application and amendments thereto.
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v Regulation (10 CFR)
Compliance 50.33 This regulation requires the license appli-cati >n to contain certain general informa-tion such as identification of applicant, type of license sought, financial qualifi-cations of the applicant, scheduled comple-tion date, and c list of regulatory agen-cies with jurisdiction over the applicant's rates and services.
This information is provided in the Shoreham Operating License Application.
50.34 (b)
The Final Safety Analysis Report (FSAR) was initially submitted on August 28, 1975, and was subsequently docketed pursuant to 10 CFR 50.34. The FSAR contains the inform-atica requimod by rnis regulation.
The document, along tith its numerous arend-monts, has been and is undergoing extensive review by the NRC and its staff.
50.34 (c)
The Physical Security Plan for SNPS was submitted to the Nuclear Regulatory Commis-sion (NRC) in October 1977 with the most recent amendment (Rev. 4) submittti April 6, 1981.
The NRC has congleted its review of the Plan.
50.34 (d)
The Safeguards Contingency Plan for SNPS was submitted to the NRC on 3/23/79.
This plan was most recently amended on 6/10/81 (Rev. 2).
The NRC has completed its review of the Plan.
50.34a (c)
The required information pursuant to 50.34a is presented in Chapter 11 of the FSAR.
The Environmental Repcrt-Operating License stage provides the recuired information on expected releases.
50.36 (a) & (b)
The Shoreham application for an Operating License incorporates Technical Specifica-tions in accordance with the requirements of 10 CFR 50.36.
Revisions to these Technical Specifications are presently being prepared.
50.36 (c)
This regulation lists the categories which will be included in the Technical Specifi-cations, cuch as safety limits, limiting i
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Regulation (10 CF '_
Compliance 50.36 c) (Con't.)
conditions for operation, surveillance re-quirements, design features and adminis-trative controls.
All of the above listed categories are contained in the current draft Technical Specifications which are under preparation.
50.36a SNPS " Compliance with 10 CFR 50 Appendix I",
Docket 50-322, July 1976, demonstrates the design capability established to keep releases as low es reasonably achievable.
The SNPS Radiological Effluent Technital Specification will ensure that concentra-tions of radioactive effluents released to unrestricted areas are within the limits i
specified in 10 CFR 20.106 and that the semiannual effluent report requirements 4
are met.
50.37 This regulation requires the applicant to agree to limit access to Restricted Data.
As stated in the Operating License applica-tion ".
LILCO hereby agrees that it will not permit any individual to have hccess to Restricted Data until the Civil Service Commission shall have made an in-vestigation and report to the Commission on the character, associations, and loyalty of such individual and the Commission shall have determined that permitting such person to h' ave access to Restricted Data will not endcnger the common defense and security".
(paragraph II. (j))
50.38 This regulation prohibits the NRC from issuing a license to foreign-controlled entities.
LILCO's statement that it is not owned, controlled, or dominated by an alien, foreign corporation, or foreign gov-ernment is in the Operating License appli-cation for the Shoreham Nuc.loar Power S ta ti on. (see paragraph II. (d) (3) (iii) )
i 50.40 (a)
The design and operation of the facility is to provide reasonable assurance that the Applicant will comply with NRC regulations, including those it 10 CFR Part 20, and that the health and safety of the public will not be endangered.
10
Regulation (10 CFR) __
Compliance 50.40 (a) (Con't.)
The basis for LILCO's assurance that the regulations will be met and the public protected is contained in this enclosure and in the License Application and the related correspondence over the years.
Moreover, the lengthy process by which the plant is designed, constructed, and re-viewed, including reviews by LILCO's staff, G.E.
and S&W staffs, the NRC staff, the 7.C RS, and NRC Licensing Boards, provides a great deal cf assurance that the public health and safety will not be endangered.
50.40 (b)
The Atomic Safety and Licensing Board at the Construction Permit stage found LILCO to be technically and financially qualified to design and construct Shoreham.
I 50.40 (c)
Anothe consideration is that the issuance of the license is not to be inimical to the common defense and security or to the health and safety of the public.
The indi-vidual showings of compliance with partic-ular regulations contained in this enclo-sure, as well as the contents of the entire FSAR and related correspondence over the i
years, plus the lengthy process of design, i
construction, and review by LILCO's staff, i
G.E.
and S&W staffs, the NRC Staff, the ACRS, and NRC Licensing Boards provide con-siderable assurance that the license will net be inin.ical to the health and safety of the public. There is considerable assurance i
that the license will not be inimical to the common defense and security in that LILCO has an approved security plan for Shoreham Nuclear Power Station, is not con-trolled by agents of foreign countries, and has agreed to limit access to Restricted i
Data.
50.40 (d)
The final consideration of 50.40 is that applicable requirements of Part 51 have satisiied.
Part 51 concerns compliance with the National Environmental Policy Act of 1969.
LILCO submitted a Final Environ-l mental Report.
The NRC reviewed the report and published a final Environment Impact i
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l
0 i
Regulation (10 CFR)
Compliance l
50.40 (d) (Con't.)
State ent, NUREG-0285, in October 1977, pure at to 10 CFR 51.
Additionally, the ASL aas closed the environmental phase of the Ope *ating License hearings.
4 50.42 tection 50.42 provides additional "consid-erations" to " guide" the Commission in issuing Class 103 licenses.
The two consi-derations are:
(a) that the proposed activities will serve a useful purpose proportionate to the quantities of special nuclear material or source material to be utilized and (b) that due account will be taken of the antitrust advice provided by the Attorney General under subsection 105c of the Atomic Energy Act.
The "useful pur-pose" to be served is the production of electric power.
The need for the power was determined by the Licensing Board at the Construction Permit stage.
Although condi-tions affecting the need for power are constantly changing, LILCO periodically makes load projections and, in LILCO's judgment, the need for Shoreham Nuclear Station is still substantial.
As for the amount of special nuclear material or source material used, there is no reason to believe that their proportion in rela-tion to the power produced is substantially greater than that of other commercial power i
reactors in this country.
Updated anti-trust information was submitted via LILCO letter SNRC-509 from J.P. Novarro to H.R.
Denton, dated September 30, 1980.
The NRC is presently undertaking the antitrust re-view and has not yet informed the Applicant of its conclusions.
50.43 (c)
Long Island Lighting Company, which trans-nits electric energy in interstate com-merce, and sells it at wholesale in inter-state commerce, is in compliance with the regulatory provisions of the Federal Power Act.
12 A
4 Regulation (10 CFR)
Compliance 50,44 Compliance with paragraphs (a) through (d) and (f) is discussed in FSAR Section 6.2.5.
The primary containment will be provided with an inerted atmosphere as discussed ia the response to NUREG-0737, Item II.B.7 (See SNRC-608, dated July 31, 1981).
Paragraph (c) is not applicable, since the notice of hearing on the Application for the Construction Permit for Shoreham was publishet'l prior to November 5, 1970.
Paragraph (g) is not applicable, since the J
notice of hearing on the Application for the Construction Permit for Shoreham was ptished efter December 22, 1968.
j As stated the combustible gas control sys-tems for Shoreham meet the requirements of 10 CFR 50.44.
50.46 Compliance with 10 CFR 50.46 is documented.
i in th? FSAR, Section 6.3.3.
This analysis shows thit SNPS raeets 10 CFR 50.46 criteria and the ECCS equipment will perform its function in an acceptable manner.
50.46 LILCO's compliance with this regulation is as stated in this enclosure where compli-ance with Appendix R is discussed.
50.51 In the Operating License application, I.~ LCO requested that the license be issued fa r a period of 40 years.
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50.53 This regulation provides that licenses are not to be issued for activitie' at are not under or within the jurisd on of the i
United States.
The operatic"
'horeham Nuclear Power Station w.ll
' tin the United States and subjeco to e jurisdic-tion of the United States,
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is evident from the description of the facility in the i
Operating License application.
e 13 E
Regulation (10 CFR)
Compliance 50.54 This regulation specifies certain condi-tions that are incorporated in every li-cense issued.
Compliance is effected simply by including these conditions in the license when.it is issued.
- Indeed, much of 50.54 merely provides that other provisions of the law apply, which would be the case even without 50.54.
LILCO will comply with these requirements on the time-table set in the regulation.
50.55a (a) (1)
Various chapters of the FSAR discuss de-sign, fabrication, erection, construction, testing, and inspection of safety-related equipment.
For example, Section 5.2 dis-cusses the design of the reactor coolant system, Chapter 14 covers testing of var-ious satety-related systems, and Chapter 17 gives information on the quality assurance program utilized in the inspection of equipment.
50.55a (a) (2)
This subparagraph provides general informa-tion leading into subparagraphs (c) through (i) of this regulation.
50.55a (b) (1) & (2)
These subparagraphs provide guidance to be used in applying subparagraphs (c) through (i) concerning the approved edition and Addenda of Sections III and XI of the ASME Boiler and Pressure Vessel Code.
30.55a (c)
Design and fabrication of the reactor i
vessel was carried out in accordance with ASME Section (II (1965) Class A including l
Addenda through winter (1966).
Informa-l tion can be found in Chapters 3 and 5 of the PSAR.
l 50.55a (d)
Reactor coolant system piping meets the requirements of ASME Section III or ANSI l
B.31.1.
Chapters 3 and 5 of the FCAR con-tain further information and specifically, Table 3.2.1.1 outlines the applicable design codes and the associated purchase i
order dates.
l 50.55a (e)
Pumps which are part of the reactor coolant pressure boundary meet the requirements of t
I i
14 ms
Regulation (10 CFR)
Compliance 50.55a (e) (Con ' t. ) the ANSI B31.1.
Information can be found in Chapters 2 and 5 of the FSAR.
50.55a (f)
The valves which are part of the reactor coolant pressure boundary were designed and fabricated in accordance with the require-ments of ASME Section III, or ANSI-B31.1.
(See Chapters 2 and 5 of the FSAR) 50.55a (g)
Inservice inspection requirements for the Shoreham plant are to be stated in Section 4.0.5 of the Shoreham Technical tipecifica-tions and reflect the requirements of 10 CPR 50.55 a(g).
The Shoreham ISI pro-gram is being developed based on the 1977 edition through summer 1978 addenda of the ASME B&PV Code Section XI.
In addition, a pump and valve operability program has been implemented in accordance with NRC staff guidance and sections IWP and IWV of Section XI of the code.
50.55a (h)
As discussed in FSAR Chapter 7, the protec-tion systems naet IEEE 279-1971.
50.55a (i)
Fracture toughness requirements are set forth in Appendices G and H of 10 CFR 50.
Compliance with Appendices G and H is out-line.d in detail in FSAR Tables 5.2.4-1 and 2, respectively.
50.58 This regulation provides for the review and report of the Advisory Committee on Reactor Safeguards. A review by the ACRS will be scheduled.
50.59 As discussed in FSAR section 13.4.2.2, the LILCO Nuclear Review Board (NRB) shall review:
a) The safety evaluation completed under the provision of 10 CFR 50.59 for proposed 1) changes to procedures, equipment, or systems, and 2) tests or experiments to verify that such actions do not constitute an unreviewed safety l
question; b) Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.'59; and 15
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Regulation (10 CFR)
Compliance 59 (Con't.)
c) Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.
The NRB shall report to and advise the Vice President-Nuclear of their activities.
Safety evaluations of changes made to the equipment or review of tests and experi-ments to comply with 10 CFR 50.59 shall be kept in a manner convenient for review and shall be retained for at least five years.
SNPS will comply with the reporting re-quirements set forth in 10 CFR 50.59.
50.70 The Commission has assigned a resident in-spector to the SNPS.
LILCO has provided office space in accordance with the re-quirements of this section.
LILCO permits access to the Station to NRC inspectors in accordance with 10 CFR 50.70 (b) (3).
50.71 Records are and will be maintained in accordance with the requirements of Para-graphs (a) through (e) of this regulation and license.
Paragraph (e) requires that the FSAR be updated (within 24 months of the issuance of the operating license and annually thereaf ter).
Such updates will be made in accordance with this Section.
50.72 Notification of significant events to the NRC will be made in accordance with this regulation.
Initiation of the Emergency Pla.n will result in notification to the NRC Operations Center.
Any other reportable occurrence which may result during normal plant operation will be reported as speci-fied in the Shoreham Technical Specifica-tion.
I 50.90 LILCO will comply with the provisions of this section when applying for an amendment of Shoreham's Operating License.
Appendix A Compliance with the General Design Criteria of this Appendix is discus, sed in FSAR Sec-tion 3.1.
Furthermore, compliance with General Design Criteria is demonstrated throughout the FSAR and other materials which have been submitted on the docket to the N1.T.
16
~ - _.
Regulation (10 CFn)
Compliance Appendix B Chapter 17 of the FSAR describes the provi-sions of the Quality Assurance Program which has been implemented to comply with the applicable requirements of this Appen-dix.
Appendix C This regulation describes the information which is required to establish financial qualifications.
The Atomic Safety and Licensing Board at the Construction Permit stage found LILCO to be financially quali-fied to design and coastruct Shoreham.
The NRC is cur ~ently reviewing the latest information on financial qualifications by LILCO.
Appendix E This regulation sets forth the criteria for emergency planning.
LILCO submitted its emergency plan for Shoreham on May 27, 1981 via SNRC-568.
The NRC has not yet informed the applicant of the conclusions of their review.
Appendices G, H Compliance with Appendices G and H has been assessed in FSAR Section 5.2.4 and the res-ponse to SER open item #20 transmitted ic the NRC in LILCO letter SNRC-578 dated l
5/29/81.
Appendix I This Appendix provides numerical guides for design objectives and limiting conditions I
for operation to meet the criteria "as low as is reasonably achievable" for radioac-l tive material in light-water-cooled nuclear l
power reactor effluents.
LILCO has filed
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with the Commission the necessary informa-I tion to demonstrate compliance and permit an evaluation of the Shoreham Nuclear Power
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Station with respect to the requirements of Appendix I, as documented in "Shoreham l
l Nuclear Power Station - Unit 1, Compliance l
with 10 CFR 50 Appendix I" transmitted to l
the NRC via SNPS-119, dated July 30, 1976.
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Regulation (10 CFR)
Compliance Appendix J Reactor pressure boundary leakage testing for water cooled power reactors is delin-eated in this Appendix.
Compliance with these requirements is outlined in Techni-cal Specification 3/4.6.1 and FSAR Section 6.2.1.4.1.
The special testing require-ments of the Main Steam Isolation Valves are addressed in FSAR Section 3.6.1.2.
Appendix K Compliance with 10 CFR 50 Appendix K is specifically required by 1C CFR 50.46.
Compliance is documented in Section 6.3.3 of the SNPS FSAR.
Appendix R This appendix delineates general and specific requirements concerning a fire protection program and sets forth certain fire protection features required to satisfy Criteria 3 of Appendix A to 10 CFR 50.
Shoreham's compliance to this Appendix is addressed in letter SNRC-572 dated May 21, 1981.
100.10 This regulation sets forth factors to be considered when evaluating a site, such as characteristics of reactor design and oper-ation, population density and use charac-teristics of the site environs, and physical characteristics of the site.
All of the above factors have been provided in the application.
Site physical character-istics, including seismology, meteorology, geology and hydrology, and population dens-ity and site use characteristics, including the exclusion area, low population zone, and populhtion center distance, are pre-sented in Chapter 2 of the FSAR.
The FSAR also describes the characteristics of reactor design and operation.
100,11 This regulation sets forth the means to derive an exclusion area, a low population zone, and population center distance.
All the requirements of this regulation with regard to the above distances and area are met and are described in Chapter 2 of the FSAR.
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Regulation (10 CFR)
Compliance Appendix A Structures and equipment important to plant safety are protected from or designed to withstand all appropriate seismically re-lated phenomena at the plant site.
Design is based on the most severe probable seis-mic event with special consideration for the uncertainty in prediction.
Detailed I
discussions of the development of the de-sign criteria and how they are applied to the structures and equipment, are found in the following FSAR sections:
Geology and Seismology-Section 2.5 Classification of Structures, Systems, and Components-Section 3.2 Water Level (Flood) Design-Section 3.4 Seismic Design-Section 3.7 Design of Category I Structures-Section 3.8 Mechanical Systems and Components-Section 3.9, i
Seismic Design of Category I Instrumenta-tion and Electrical Equipment-Section 3.10.
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