ML18082B190
| ML18082B190 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/09/1980 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8009180413 | |
| Download: ML18082B190 (52) | |
Text
Public Service Electric and Gas Company 80 Par~ Place Newark,. N.J. 07101 Phone 201/430-7000
- september 9, 1980 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Frank J. Miraglia, Chief Licensing Branch 3 Division of Licensing Gentlemen:
SUPPLEMENTAL INFORI'1ATION COMPLIANCE WITH NRC REGULATIONS NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 PSE&G's letter dated September.3, 1980 submitted a listing of each regulation in 10 CFR Parts 20, 50, and 100, and where they are addressed in the license application.
PSE&G believes that Salem No. 2 complies with the applicable regula~ions~ except in those cases where specific exemptions or alternate means have been justified and approved by the NRC staff.
Our confidence in this conclusion is based on the references provided in the September 3, 1980 submittal, together with the detailed review of Salem 2 by the NRC staff.
PSE&G's design and review process, quality assurance program, and the independent review by the NRC staff and the ACRS provide reasonable assurance that the health and safety of the public will be protected.
Should you have any questions in this regard, do not hesi-tate to contact us.
r1:;;;rrs, R. L. Mittl General Manager -
Licensing and Environment Engineering and Construction CC:
Mr. Leif Norrholm Salem Resident Inspector EPOlO The Energy People
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COMPLIANCE OF SALEM NUCLEAR GENERATING STATION, UNIT 2 WITH PARTS 20, 50 AND 100 OF THE NRC REGULATIONS 10CFR TITLE 10, CODE OF FEDERAL REGULATIONS Regulation
( 10CFR) 20.l(a) 20.l(b) 20~l(c) 20.2 20.3 M P80 89 01/4 Compliance This regulation merely states the general purpose for which the Part 20 regulations were established and does not impose any independent obliga-tions on licenses.
This regulation describes the overall purpose of the Part 20 regulations to control the possession, u~e and tr~nsfer of licensed material by any licensee, such that the total dose to an individual will not exceed the standards prescribed therein.
It does not impose any independent obli-gations on the licensees.
Confoirmance to the ALARA principle stated in this regulation is ensured by the implementation of Company pol-icies and appropriate Technical Spec-ifications and health physics proce-dures.
Chapters 11 and 12 of the FSAR describe the specific equipment and design features utilized in this effort.
This regulation merely establishes the applicability of the Part 20 regulations and imposes no independ-ent obligations on those licensees to which they apply.
The definitions contained in this -
regulation are adhered to in all appropriate Technical Specifications and procedures, and in applicable sections of the FSAR.
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Regulation (10CFR) 20.4 20.5 20.6 20.7 20.101 20.102 M P80 89 01/5 Compliance The units of radiation dose specified in this regulation are accepted and conformed to in the FSAR, Technical Specifications and all applicable station procedures.
The units of radioactivity specified in this regulation are accepted and conformed to in the FSAR, Technical Specifications and all applicable station procedures.
This regulation governs the interpre-tation of regulations by the NRC and does not impose independent obliga-tions on the licensees.
This regulation gives the address of the NRC and does not impose independ-erit obligations on the licensees.
The radiation dose limits specified in this regulation are compli.ed with.
through the implementation of and adherence to administrative policies
_and controls and app~opriate health physics procedures* developed for this purpose.
Conformance is documented by the use of appropriate personnel moni.toring devices and the mainte-nance of required records.
When requ~red by this regulation, the accumulated dose for any individual permitted to exceed the exposure limits specified in 20.lO(a) is de-termined by the use of Form NRC-4.
Appropriate health physics pro.cedures and administrative policies control this process.
Regulation (10CFR) 20.103(a) 20.l03(b) 20.103(c) 20.103(d)
M P80 89 01/6 Compliance Compliance with this regulation is ensured through the implementation of appropriate health physics procedures relating to air sampling for radio-active materials, and bioassay of individuals for internal contamina-tion.
Administrative policies and
- controls provide adequate margins of safety for the protection of indi~
viduals against intake of radioactive materials.
The systems and equipment described in Chapters 11 and 12 of the FSAR provid~ the capability to minimize these hazards~
Appropriate process and engine.ering controls and equipment, as described in Chapters 11 and 12 the FSAR, are installed and operated to maintain levels of airborne radioactivity as low as practicable.
When necessary, as determined by station administra-tive guidelines, additional piecau-tionary procedures are utilized to limit the potential for intake of radioactive materials.
The station respiratory protection procedures implement the requirements of this regulation by ensuring the proper use of approved respiratory protection equipment.
The station respiratory protection procedures in:-
corporate the guidance of Regulatory Guide 8.15, "Acceptable Programs for Respiratory Protection."
This regulation describes further re-strictions which the Commission may impose on the licensee.
It doe.s not
Regulation (10CFR) 20.103(e) 20.103(f) 20 *. 104 20.lOS(a) 20.lOS(b) 20.106(a)
M P80 89 01/7 Compliance impose any independent obligations on the licensees.
The notification specified by this regulation was made as required* on March 4, 1977.
The respiratory protection program is in conformance with the requirements of 20.103(c).
- Conformance with this regulation is assured by the appropriate Company policies regarding employment of individuals under the age of 18 and the station health physics procedures restricting these irtdividuals' access to the station's restricted areas
- Chapter 11 of the FSAR provides the information and related radiation dose assessments specified by this regulation.
The radiation dose rate limits speci-fied in this reg.ulation are complied with through the implementation of station procedures, Technical Speci-fications, and administrative poli-cies which control the use and trans-fer of radioactive materials.
Appro-priate surveys and monitoring device~
document this compliance.
Conformance with the limits specified in this regulation is assured through the implementation of station proce-dures and applicable Technical Speci-fications which provide adequate sampling and.analyses, and monitoring of radioactive materials in effluents
Regulation (10CFR) 20.106(b) 20.106(c) 20.106(d) 20.106(e) 20.106(f) 20.107 M P80 89 01/8 Compliance prior to and during their release.
The level of radioactivity in station effluents is minimized to the extent reasonably achievable by the use of appropriate equipment designed for this purpose, as described in Chapter 11 of the FSAR.
PSE&G 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 for in these regulations.
Appropriate allowance for dilution and dispersion of radioactive efflu-ents are made in conformance with this regulation, which is in conform-ance with the Environmental Technical Specifications.
This regulation provides cri te-ria by which the Commis*sion may impose fur-ther limitations on rele~ses of radioactive materials made by a li-censee~ It imposes no independent obligations,on the licensees.
_______ This regulation merely states that the provisions of 20.106 do not apply to disposal of radioactive material into sanitary sewerage systems.
It imposes no independent obligations on the licensees.
Th is regu,lation merely clarifies that the Part 20 regulations are not in-tended to apply to the intentional exposure of patients to radiation for the purpose of medical diagnosis or
e
. Regulation (10CFR) 20.108 20.201 20.202{a)
M P80 89 01/9 Compliance therapy.
It does not impose any independent obligations on the licensees.
Necessary bioassay equipment and pro-cedures, including whole body count-ing, are utilized at the station to determine exposure of individuals to concentrations of radioactive mate-rials.
Appropriate health physics procedures and administrative poli-cies implement this requirement.
The surveys required by this regula-tion are performed at adequate f re-quencies and contain such detai.l as to be consistent with the radiation hazard being evaluated.
When neces-sary, the Radiation Exposure Permit system established at the station provides for detailed physical sur-veys of equipment, structures and work sites to determine appropriate
.levels of radiation protection.
The station's health physics procedures require these surveys and provide for their documentation in s.uch manner as to ensure complia-nce with the regula-tions of 10CFR Part 20.
The health physics procedures set forth policies and practices which ensure that all individuals are sup-plied with, and required to use, ap-propriate personnel: monitoring equip-ment.
The Radiation Work Exposure Permit system is established to pro-vide additional control of personnel working in radiation areas and to en-sure that th~ level of protection af-forded to these individuals is con-
Regulation (10CFR) 20.202(b) 2.0. 20 3 (a) 20.203(b) 20.203(c)
M P80 89 01/10 Compliance sistent with the radiological hazards in the work place.
The terminology set forth in this regulatiori is accepted and is conformed to in all applicable station procedures, ~echnical Specifications, and those portions of the station health physics procedures in which.its use is made.
All materials used for labeling, posting, or otherwise designating radiation hazards or radioactive ma-terials, and using the radiation sym-bol, conform to the conventional de-sign prescribed in this regulation
- This regulation is complied with through the implementation of appro- _
priate health physics procedures re-1.ating to posting of radiation areas,_
a-s* defined in 10CFR, Section 2.0
- 2.0 2 ( b) ( 2)
- The requirements of this regulation f.or "High Radiation Areas" are con-formed to by the implementation of the Technical Specifications and ap-propriate health physics procedures.
The controls and other protective measures set forth in the regulation are maintained under the surveillance of the station's health physics group.
It should be noted that Technical Specification 6.12.l provides alter-nate access control methods to be ap-plied "in lieu of the 'control de-vice' or 'alarm signal' required by
Regulation (10CFR) 20.203(d) 20.203(e) 20.203(f) 20.204 2.0.205 M P80 89 01/11 Compliance paragraph 20.203(c) (2) of 10CFR20,"
which will prevent unauthorized entry into a high radiation area.
Each Airborne Radioactivity Arei,* as defined in this regulation, is re-quired to be posted by provisions of the appropriate health physics proce-dures.
These procedures a*lso provide for the surveillance requirements necessary to determine airborne radioactivity" levels.
The area and room posting require-*
ments set forth in this regulation pertainin~ to radioactive materials are complied with through the imple-mentation of appropriate health phys-ics procedures.
The container labeling req.uirements set forth in this regulation are com-*
plie.d with through the implementation o.f appropriate health physics proce-dures.
The posting requirement exceptions described in this regulation are used where appropriate and necessary at the station.
Adequate controls are provided within the station health physics procedure.s to ensure safe and proper application of these excep-t*ions.
All of the requirements of this regu-la*tion pe:rtaining to procedures for picking up, receiving, and opening packages of radioactive materials are implemented by the appropriate health physics procedures.
These procedures
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Regulation (10CFR) 20.206 20.207 20.301 20.302 20.303 M P80 89 01/12 Compliance also provide for the necessary docu-mentation to ensure an auditable record of compliance.
The requirements of 10CFR19.12 refer-red to by this regulation are satis-fied by the training programs con-ducted at the station.
Appropriate health physics procedures set forth requirements for all radiation workers to receive this instruction on a periodic basis.
The storage and control requirements for licensed materials in unrestrict-ed areas are complied with and docu-mented through the implementation of station health physics procedures.
The general requirements for waste disposal set forth in this regulation are compl.ied with through station health physics procedures, the Tech-nical Specifications, and the provi-sions of the station license.
Chap-ter 11 of the FSAR describes the Solid Waste Disposal System installed at the station.
No such application for propq~ed dis-posal procedures, as described in this regulation, has been made or is currently being contemplated by PSE&G for Salem Unit 2.
No plans for waste disposal by re-lease into sanitary sewerage systems, as provided for in this regulation, are contemplated by the station, nor is this practice currently utilized.
Regulation (10CFR) 20.304 20.305 20.401 2.0.402 20.403 M P80 89 01/13 Compliance Disposal of wastes by burial in soil (i.e., onsite burial), as provided for in this regulation, is not per-formed currently or being contem-plated by the station.
Specific authorization, as described in this regulation, is not currently being sought by PSE&G for treatment or disposal of wastes by incineration.
All of the requirements of this regu-lation are complied with through the implementation of appropriate Tech-nical Specifications and health physics procedures pertaining to rec-ords of surveys, radiation monitoring and waste disposal.
The retention periods specified for such records are also provided for in these speci-fications and procedures.
The station has established an appro-priate inventory and control program to ensure strict accountability for all licensed radioactive materials.
Reports of theft or loss of licensed material are required by reference to the regulations of 10CFR in the Tech-nical Specifications.
Notification of incidents, as des-cribed in this regulation, are as-sured by the requirements of the Technical Specifications, and health physics procedures, which also pro-viGe for the necessary assessments to determine the occurrence of such incidents.
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Regulation (10CFR) 2 o. 2 04 20.205
. 20.406
- 20.407 2.0. 408 20.4'09 20 *. 501 M P8*0 89 01/14 Compliance This regulation was deleted effective September 17, 1973 (38 Fed. Reg.
2 2220)
- Reports of overexposures to radiation and ths occurrence of excessive levels and concentrations, as re-quired by this regulation, are pro-vidsd f~r by reference in the Tech-nical Spec.if ications. and in appro-priate h~alth physica procedures.
This regulation was.deleted August 17, 1973~ effective Septem-
- . ber 17, 1973 (38 Fe.a. Reg. 22220).
The pe.rsonnel monitoring report re-quired by this regulation is express-.
ly provided for by the Technical Specif:icat.ions.
- Appropriate heal th physics procedures establish the data bas~ f~om which this report is generated *..
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The report of radiation exposure re-
~uired by this regulation upon termi-
. nation of an individual'~ s employment or wcrk ass.ignmen t is generated through the provisions of a station he~lth phy~ics procedure.
The notification and reporting re-quirements o,f this regulation, and th0se referred to by it, are satis-fied by the provisions of a station health physics procedure.
This regulation provides for the granting of exemptions from 10CFR Part 20 regulations, provided such exemptions are authorized by law and
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Regulation (10CFR) 20.502
- 20. 6.01 SO.l so *. 2 S0.3 so. 4*
S0.10
- 50. l.l M P80 89 01/15 Compliance will not result in undue hazard to
. life or property.
It does not impose independent obligations on the licensees.
This regulation describes the means by which the Commission may impose upon any licensee requirements which are in addition to the regulations of Part 20.
It does not impose i.nde-pendent obligations on the licensees.
This regulation describes the reme-die.s which the Commis*sion may obtain in order to enforce its regulations, and sets forth* those penalties or punishments which may be imposed for violations of its rules.
It does not impose any independent obligations on the *licensees.
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This regulation states the purpose of*
the Part SO regulations and does not impose a*ny independent obligations* on the* 1 icensees.
This regulation defines various terms and does not impose independent obli-gations on tpe licensees.
This regulation governs the interpre-*
tation of the regulations by the NRC and does not impose independent obli-gations on the licensees.
This regulation gives the address of the NRC and does not impose. independ-ent obligations on licensees.
These regulations specify the types of activities that may not be under-
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- Regulation (10CFR) 50.12 50.13 50.20 50.21 50.23 50.30 M P80 89 01/16 Compliance taken without a license from the NRC.
PSE&G does not propose to con-duct any such activities at Salem 2 without an NRC license.
This regulation *provides for the granting of exemptions from 10CFR Part 50 regulations, provided such exemptions are authorized by law and will not endanger life, or property or. the common defense and security and are otherwise in the public interest.
It does not impose inde-pendent obligations on the licensees.
This regulation states that a license applicant need not design against acts of war.
It imposes no independ-ent ~bligations on licenses.
These regulations describe the types of licenses that the NRC issues.
Th.ey do not addres*s the substantive requirements that an applicant must satisfy to qualify for such licenses.
This regulation sets forth procedural requirements for the filing of li-c*ense applications, such as the num-ber of copies of the application that must be provided to the NRC.
PSE&G has substantially complied with the procedural requirements in effect at the time of filing of its license application and the amendments to it.
In particular, 10CFR50.30(f) requires that a license application must be accompanied by any Environ-mental Report.
PSE&G has submitted such an Environmental Report.
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Regulation (10CFR) 50.31 50.32 50.33 50.33a 5:0. 3 4 (a) 50 *. 3 4 ( b)
M P80 89 01/17 Compliance Theae regulations essentially permit more efficient organization of the license application and impose no in-dependent obligations on the lic.ensees.
This regulation requires the license application to contain certain gen-
.eral information, such as* an. identi-fication of each applicant, informa-tion about. each applicant_* s financial qualifi.cat.ions, and a list of regula-
- tory agencies with jurisdiction over the applicants'* rate*s and services.
This information is provided* in the o.perating 1 icense application for
-Sal.em Unit 2:..
- ):,
This re.gulation requires appii:cants*
f0r constructio.n. permits to submit.
informa ti.on required for anti trust revi~w..Inasmuch as* the construction o.f s*a lem Uhi t 2. was 1 icens*ed pursuant
. to Section 104'b of the Atomic Energy Act. prior to December 19, 1970, this
.regulation is not applic.abl.e.
This re.gulation gove,rns the contents o.f the Preliminary Safety Analysis Re.port and *is relevant to the con-struction permit stage rather than the ope-rating lice.nse stag.e.
A Final Safety Analysis Report ( FSAR) has been prepared and. submitted, which. addresses in the chapters ind i-cated the information required:
( l*)
site evaluation factors -
Chap-t.er 2
Reg.ulation (10CFR)
M P80 89 01/18
( 2)
( 3)
( 4)
( 5)
( 6) ~omplia-nce structures, systems and compo-nents - Chapters 3, 4, 5, 6, 7, 8, 9, 10, 11 radioactive effluents and radia-tion protection - Chapter 11.
design and performance evalua-tion - E:ccs performance is dis-cussed and shown-to meet the re-quirements of 10CFRS0.46 in Chapters 6 and 14.
results of Research and Develop-ment programs -- Chapter 1-(i) organizational structure -
Chapter 12
( i L) manage.rial and administra-tive controls - Chap-ter 12 and FSAR Appendix D discusses compliance with the quality assurance re-quirements of Appendix B.
(iii) plans for preoperational testing and initial opera-tion - Chapter 13 (iv1 plans f6r conduct of nor-mal operations - Chap-te:r 12.
Surveillance and periodic testing is speci.-
f ied in the Te chnica-1 Specifications.
(v) plans for coping with emergencies - Emergency Plan - Chapter 12
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Regulation
( l.OCFR) 5.0. 3 4 ( c}
50.34(d}
50.34a(a}
( b}
50.34a(c}
M P8 0 8 9 01/19 (vi) Compliance Technical Specifications -
Appe.ndi x A of the Oper-a ting License.
The technical specifications appended to the license were prepared by the staff in conjunction with the applicant.
(vii} This section is not appli-cable since the operating license application was filed prior to* February 5, 1979 (7}
technical qualifications -
Chap-ter 12 (8}
operator requalification program Incorporated into the applica-tion by our letters dated August 1, 1980 and August 20, 1.980.
A physical security plan has been prepared and is currently implemented *.
A safeguards contingency plan is in-cluded in the physical security plan.
These regulations cover the contents of the Preliminary Safety Analysis Report on systems to control the re-lease of radioactive effluents.*
The Final Safety Analysis Report which has been submitted addresses systems to control the release of radioactive effluents in Chapter 11.
Regulation
( l.OCFR)
SU.35 50.36
- 50. 36.a M P8 0 8 9 0 1/2 0 Compliance In addition, information concerning the methods used to control the re-lease of radioactive effluents in conformance with Appendix I to 10CFRSO was supplied to the Commis-sion in our letters dated June 21, 1976, October 26, 1976 and Decem-ber 1, 197 6.
This regulation is. relevant to the c6nstructiori permit stage rather than the operating stage.
Proposed Technical Specifications were submitted with the applicatioi.
The Technical Specifications appended to the license were prepared by the staff in conjunction with the appli-c.ant.
(1) safety limits and limiting safety settings, ( 2) limiting c.ondi tions fo.r operation, ( 3) surveillance require--
ments, ( 4) design features', and ( 5) administrative controls.
The Environmental Technical Specif i-cations include specif1cations which demonstrate* h.ow the PSE&G Salem Sta-tion will comply with 10CFRSO.34a (as Low As Reasonably Achievable Guid-ance).
These specifications are based upon the concluding statement of position of the Reg.ulatory Staff (RM-50-2) and a:ssure that concentra-tions of radioactive effluents re-1.ea*sed to unrestricted areas are within the limits specified in 10CFR20.
The reporting requirements of 50.36(a) (2) are also included in these specifications.
The Salem Sta-
Regulation
( 10CFR) 50.37 50.38 50.39 50.40 S0.40(a)
M P8.0 89 01/21 Compliance tion operating procedures have been established in accordance with this regulation.
This regulation requires the appli-cants to agree to limit access to re-stricted data.
The agreement to do so is in the operating license ap-plication for Salem 2.
This regulation prohibits the NRC from issuing a license to foreign-controlled entities.
The owners' statements that they are not owned, controlled, or dominated by an alien, foreign corporation, or foreign gov-ernment is in the ope*ra ting 1 icense application for Salem 2.
This regulation provides that appli-cations and related documents may b.e made available for public inspec*-.
ti.on..
This imposes no direct obliga-tions on applicants and licensees.
This regulation provides considera-tions to "gu.ide" the Commission in g:ra*nting licenses, as follows:
The design and ope*ration of the facility should provide reasonable assurance that the applicant will comply w.ith. NRC regulations, includ-ing those iri 10CFR Part 20, and tha*t the health and safety of the public will not be endangered.
The basis for PSE&G's assurance that the regu-lations will be me.t and the public protected is contained in the license application, Technical Specifications and the related correspondence over
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- Regulation (10CFR) 50.40(b) 50.40(c)
M P80 89 01/22 Compliance the years.
Moreover, the lengthy process by which the plant is de-signed, constructed, and reviewed, including reviews by PSE&G's own staff, the NRC Staff and the ACRS provides a great deal of assurance that the public health and safety will not be endangered.
Another consideration is that the ap-plicants be technically and f inan-cially qualified.
These qualifica-tions are provided in Amendment 44 to the Operating License application *.
Another consideration is that the is-suance of the license is not to be inimical to the common defense and security or to the health and safety of the public.
The individual show-ings of compliance with particular regulations contained in this Attach-ment, as well as the contents of the entire FSAR and related correspond-ence over the years, plus the lengthy process of design, construction, and review by PSE&G, its NSSS vendor, and the NRC, provide PSE&G with considerable assurance that issuance of the license will not be inimical to the health and safety of the public.
As for the common defense aQd the security, there is consider-able assurance that the license issu-ance will not be inimical in that PSE&G has a qualifying security plan for the power station, that the owners are not controlled by agents of foreign countries, and that the owners have agreed to limit access to restricted data.
Regulation (10CFR)
S0.40(d)
S0.4l(a)
S0.4l(b) 50.4l(c) 50.42 50.43 M P80 89 01/23 Compliance The final 50.40 "consideration" is that the applicable requirements of Part 51 have been satisfied.
Part 51 concerns compliance with the National Environmental Policy Act of 1969.
PSE&G has submitted an Environmental Report, the NRC Staff has issued an Environmental Impact Statement.
In addition, Environmental Technical Specifications have been issued for Salem 2; thus, the applicable requirements have been met.
This regulation applies to uses of special nuclear material for medical therapy and is thus not applicable to Salem Unit 2
- This regulation provides guidance to the Commission relating to considera-tions appropriate to the issuance of a 104 License such that the. Commis-sion will permit the conduct of wide-spread and diverse research and de-ve.1opment.
The Commission issued a Class 104b Construction Permit for Salem 2.
In accordance with Section 102b of the Act, an operating license for this facility was issued pursuant to 104b.
The research and develop-ment programs associated with the Salem facility are described in Sec-tion 1 of the FSAR.
This section imposes no independent obligation on the licensees.
The application for an ope*rating license is for a Class 104 license and thus these sections are not applicable.
Regulation (lOCF~)
50.44 50.45 50.46 M* ps-o sg 01;24 Compliance The Salem combustible gas control system is described in FSAR Section 14.3 *. 6.
The system is designed to maintain the concentration of hydro-gen at a safe level following a LOCA without the need for containment purging.
The system consists of two electric recombiners permanently in-stalled in the containment of each Salem unit *.
As d.escribed i.n FSAR Section 14.3.6.5, each recombiner is operated from a separate control panel located ou,tside the Containment Bu.ilding in the Auxiliary Building.
FSAR Sect:ion 14-. 3.6 discusses the three s*ources of hydrogen, as re.-
quired by 50 *. 4-4.(a}, and the analyses of each sourc.e.
p:sAR Figure 14. 3-39a plots the re-sults of* the analyses of the three sources and demonstrates that the buildup of hydrogen takes many days during which the recombiners can be started as required by 50 *. 4 4 ( c).
To th~-- extent this regulation pro-vid:es standards for c*onstruction per-mits rather the operating licenses, it is not material to the present application.
To the extent that a m:aterial alte*ration to the fa.cility might be made in the future, the s:ta-ndards herein will be addres:sed in any application.
F.SA-R Sections 6. 2 and 14.1 describe the Emerg.ency Co re Cooling System and.
Regulation (10CFR) 50.,50 50 *.51 50.52 SC>.53 M P.80 89 01/25 Compliance the methods used to analyze ECCS per-formance following a postulated loss of coolant accident.
In Amendment 43 to the FSAR, PSE&G provided the results of a LOCA-ECCS analysis for Salem Unit 2 using the February 1978 version of the Westing-h.ouse Evaluation Model which was ap-prove.a by the Commission in a letter to Westinghouse dated May 13, 1976.
The analysis is based on an*overall peaking factor of 2 *. 3 2 and provided results in co~pl.iance with the cri-teria of 10CFR50 *. 46.
Th.is regulation provides that the NRC will issue a license upon determining that the application meets the stand-ards and requirements of the Atomic En.ergy Act and the regulations there-to.
It also requires that the nece~
sary.notif i.cations to other ag.encies or bodies hav~ been duly made.
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This regulation specifies the maximum du.ration of 1 icenses.
Compliance will be affected s*imply. by the Com-mission's writing the 1 icense s.o as to. comply.
This re,gulation provides for the combining i.n a sing.le license. of a n;urtlber of activi t:le:s.
It imposes no independent obligation on the licensee.
This regulation provides that li-censes are not to be issued for ac--
t.ivities that are not under or within the jurisdiction of the United
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Regulation (10CFR) 50 *. S4 SO.SS S0 *.55a(a) (1)
M PSO 89 01/26 Compl ia*nce States.
The operation of Salem 2 will be within the United States and s~bject to the jurisdiction of the United St~tes, as is evident from the description of the facility in the operating license application.
This regulation specifies certain conditions that are incorporated in every_ license issued or deemed in-corporated. *Such regulation is thus self-executing and imposes no direct obli.gation on 1 icensees.
The low power license presently in effect for Salem 2 expressly states. that it is subject to the conditions contained in 1 OC FR 5 0. 5 4..
Th is regulation address*es conditions of construction permits, not operat-ing licenses, and so it is not ma-te.rial at this point.
The design., fabrication, construction and testing standara*s for safety re-late.d structures, systems and compo-nents are discussed in various chap-ters pf the FSAR as noted below:
Chapter 4 Conta*inment Structure and Systems - Chapter 5 Emergency Core Cooling System -
Chapter 6 In:struments and Controls -
Chapter 7
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Regulation (l.OCFR) 50.55(a) (2) 5 0 ~ 5 Sa ( b ) ( 1 )
50 *. 55a(b}(2) 50.SSa(c}
50.55a(d}
SCJ.: 5 Sa.( e)
M P80 89 01/27 Compliance Electrical Systems - Chapter 8 Aux i 1 ia-ry and Emergency Sys-tems -
Chapter 9 Initial Tests and Operations -
Chapter 13 The Quality Assurance program u t i 1 i z e.d at Sa 1 e rn i s des c r i.be d in &SAR Appendix D~
The codes utilized in fabrication. of various safety related components are de.fined in the applicable chapters* of the FSAR as outlined under our review of 5 0. 5 Sa (a} ( 1} above
- These paragraphs provide guidance concerning the approved edition and a.ddenda. of Se ct ion I II a.nd XT of the
.ASME Boiler and Pr.e,ssure Vessel Cod.e.
De-s*ign* and fabrication of the* rea.ctor vessel was carried out in accordance*
with ASME Se.ctio.n I.II (1965} Class A,,
with addenda through winter, 1.966.
Inf6r~ation can be found in Ch~pter 4 Section 4~. 2. 2.1 o.f the FSAR*.
Rea.ctor coolant system piping meets the* requirements of USAS B31.l.O (1967).
Information can be found in Chapte*r 4, Section 4.* 2. 2. 6 of th*e
- PSAR.
Th.e. Reactor Coolant Pumps are de-signed to the criteria of ASME Sec-ti6n III a~ defined in FSAR Table 4.1-12 anc:t Question 4.13.
J
("
\\
Regulation (10CFR) 50.55a(f) 50.55a(g) 5*0.55a( h)
S*O. 5*5a { i )
M P80 89 01/28 Compliance As defined in FSAR Question 4.13, valves within the Reactor Coolant System boundary are designed in ac-cordance with ASA B31.l (1955) and the requirements of ASA 816.5, and MSS-SP-66, 1964 or ASME III, 1968.
Inservice Inspection (ISI) require-ments are delineated in this part and ate specified in the Uhit 2 Technical Specifications, Sections 4.2~
4~4.5~0, 4.4.10.l and 4.4.10.2.
As permitted by this part and the Technical Spec.-i.f ications, certain exemptions (see FSAR Chapter 4)* have been requested and granted for the inservice inspection of various systems and the inservice testing of various pumps and valves.
Suppl.ement 4 o*f the Sta.ff's SER for Sal.em 2.,. s-ection 5. 3 provides a discuss*ion of preservice inspection a*na* inservice testing of pumps.and valves...
In particular, the pump and valve program has been accepted pend-ing. certain furthe*r review.
Addi-tional information on ISI can be found i.n F*SAR Chapter 4, Section 4.5 *.J *.
As discussed in Chapter 7 of FSAR and Sta,ff SER.
The protection systems meet IEE*E 279-1.971.
Fracture toughness requirements are set forth in Appendices G and H of 10CFRSO.
Technical Specifications re.quire the use o-f reactor vessel material irradiation surveillance
Regulation (10CFR) 50.55a( j) 50.56
- 50. 5.7 (a)
M P80 89 01/29 Compliance specimens and updating of the "heat-up" and "cooldown" curves given in the Technical Specifications.
Fur-ther information is provided in the FSAR Chapter 4, Section 4. 5.1 con-cerning the irradiation surveillance pr.ogram and in the discussion of Appendices G and H.
This se.cti.on clarifies preceding sections of 50.SSa.
Th is re.gu.lation provides that the Commis.sion. will, in the absence of good cause shown to the* contrary,
- i.ssu.e an operating license upon com-pletion of the construction of a f ac-il ity in compliance with the terms a,nd conditions of the construct-ion pe:rmi ts.
This imposes no.independ*en t obligations on the applicant.
This regulation requires the Commis-s:io.n to. mak.e certain f i11dings prior to the is*suance* of an operating. li-cense.
These findings* have already been. made for Salem 2 in connection with* the issuan.c*e of the license.for f*u.e.1 load in.g and low power te*sting, a,n,a t*n.ey can also be,made for full power operation for the reasons given ip this Attachment s:p~.c.ifically:
(1)
Cons*tru:ction of the fac:ility ha*s seen substatially completed in
<::'onfermi ty with the costru.ction pe.rrni t and th.e application as a,mended.
Conformance of. th.e fa.ci.li.ty to th.e NRC rules and reg.u-.la.tions and the Act, a.s
Regulation (10CFR)
M PBO 89 01/30 Compliance implemented by the regulations, has been demonstrated by the application.
(2)
The Technical Specifications and resulting operating procedures provide as*surance that the unit will operate in conformity with the application as amended and with the rules and regulations, as documented in the Sa.lem license.
(3)
The application demonstrates that the facility can be operat-ed without endangering the health and safety of the* public and in compliance with the regu-lations, as noted above.
(4)
The applicati.on demonstrates that PS*E&G is technically and the-owners financially qualified to operate the unit *
. (5) *.The applicable provision.s of 10CFRl 40 have been sa.tisifed.
The indemnity agreement B-74 for the Salem 2 station has been amended to include t.Jnit 2.
( 6)
The approved Security Pla.n as-sures that s:pecia1 nuc1ear ma-terial is be:ing appropria-tely s,a.fe.guarded.. The a.pplic.ation demonstrates that th.e operation of the unit will not be inimical to the heal th. and safety of th.e public
- Regulation -
(10CFR)
- 50. 5T(b) 50.57(c) 50.58 50.59 50.70 50.71 M P80 89 01/31 Compliance The license, as issued, will contain appropriate conditions to assure that items of construction or modification are completed on a schedule accept-able to the Commission.
Since no operating license hearing was held for Salem Unit 2, this sub-section is inapplicable.
This regulation provides for the re-view and report.of the Advisory Com-mittee on reactor Safeguards.
The ACRS has reviewed the operating li-cense a.pplic-ation for Salem 2 and re--
poried the findings to the Commission.
Th is regulation provides for the l.i-censing of certain changes, tests, and experiments at a. licensed facil,-
ity.
Technical Specifications and procedures provide implementation of*
this regulation.
Th.e Commission has assigned resident inspectors to the Salem 2.
PSE&G has*
provided office space in accordance with the requirements of this sec-tion.
PSE&G permits access to the station to NRC inspectors in accord-ance with 50
- 7 0 ( b) ( 3)
- Records are and will be maintained in a.ceordance with the requirements* of sections (a) through (e) of this reg-u.lation and the license.
Section (e) requires that the FSAR be updated by July 22, 1982, and annually there-af.ter.
Such updates will be made *
/
Regulation (10CFR) 50.72 50.80 50.81 50.82 50.90 50.91 50.100 50.101 50.102 50.103 M P80 89 01/32 Compliance Notification of significant events to the NRC will be made in accordance with the requirements in this regula-tions.
This regulation provides that li-censes may not be transferred without NRC consent.
No application for transfer of a license is involved in the Salem 2 proceeding.
This regulatiori permits the creation of mortgages, pledges, and liens on li.censed facilities, subject to cer-tain provisions.
The regulation pro-hibits secured creditors from violat-.
ing the Atomic Energy Act and the Commission's regulations.
This regulation provide.s for the termination of licenses.
It does not apply to Salem 2 because PSE&G has not requested the termination of a license.
This regulation governs applications for amendments to licenses.
Future request for license amendments will be made in accordance with these re-qu.irements.
This re.gulation provides guidance to the NRC in issuing licens.e amend-ments.
These regulations govern the revoca-tion, suspension, and modification of licenses by the Commission for any material false statement in a license application or for failure to con-struct or operate the facility in
Regulation (10CFR) 50.109 50.110 Appendix A GDC 1 M P80 89 01/33 Compliance accordance with the provisions of the Atomic Energy Act regulations, li-cense, permit or orders of the Com-mission.
No such circumstances are present in the Salem 2 proceeding, therefore these regulations are not applicable.
This regulation specifies the condi-tions under which the NRC may require the backfitting of a facility.
The regulation imposes no independent ob-ligations on a licensee unless the NRC proposes a backfitting require-ment.
This regulation governs enforcement of the Atomic Energy Act, the Energy Re-Organization Act of 1974, and the NRC 's reg.ulations and orders.
No en-forcement action is at issue in the Sa.lem 2 proceeding, and so this regu-lati.on is not applicable.
In general, FSAR references cited below may have been supplemented by responses to Staff questions on each FSAR section.
A general discussion of compliance to the GDC is d-ocu-mented in the FSAR answer to Staff question #1.32 and in FSAR Appen-dix F.
The Staff SER paragraph 3.1 identifies compliance with the G-DC.
The following information supplements these sources.
FSAR Section 1. 3 describes the gen-eral design cri te.ria a-nd quality standards.
A quality assurance pro-gram has been established and imple-mented which assures that structures
Regulation (10CFR)
GDC 2 GDC 3 GDC 4*
M P80 89 01/34 Compliance systems and components satisfactorily perform their safety program.
The quality assurance program is des-cri.bed in FSAR Appendix D.
The design of safety related struc-tures, systems and components with respect to withstanding natural phenomena are dis.cussed in various chapters o.f* the --FSAR as outlined under our discussion on 50.SSa(a) (1) above.
FSAR Chapter 9 describes* in general the measures which have been take.n to minimize the probability and effects*
of fires and e.xplosions.
Section 9.8~2 describes the fire detection a,nd. protection sys:tems.
In add.i tion, the SER, Suppleme*nt 4:,
- p. 9-2 state,s th.e* NRC concluded that the fire p-rotec.tion prog.ram meets GDC 3.
To fu.rther assure th0e ability of the plant to withstand the damag-in.g e*ffect.s of fires* that occur we have committed to addi tiona*1.fire protection system improvements *.
FSAR Sections* 4-.2. 4 and 14. 5 des-cribes the design features used to a.c:commodate the ef*fects of, ana be c:omp_atibl.e with the envir0nmenta1 c.enclitions assoc-iated with all mode's of 01)eration and pos*tula.ted accidents.
Cha*J!>ters 4 and 14 provide information ct.:)ncerning the specific desi.gn f ea-tlil'res for prot.ecti.on against mis-s*il.es, jet imp ing,emen.t and pipe rup-
Regulation (10CFR)
GDC 5 M P80 89 01/35 Complianc.e ture.
Turbine generated mis-siles are addressed in Appendix G of the FSAR.
Provisi6ns for qualification of equipment for all postulated environ-ments are described in serveral sec-tions of the FSAR, particula*rly in the answer to the staff's questions found in Sections 5 and 7.
In add i-t ion, the results of a review of all e.lectr ica 1 e_qui pm en t against the new.
Staff criteria in NUREG-0588 has been completed.
This review has c.ohfirmed that most electr.ical equipment has be:en adequately demonstra-ted to. be qu.al.ified f'or its expected service environments.
Juitification in the form of additional evaluations and documentation has been provided to the s*taff for operation of the unit pending completion of the environmen-tal qualification review..
Th.i.s will be completed on a sch.edule in ac-cordance w i.th the Cammi ss:ion I s memo-randum and Order of May 2J, 19*80, and applicable licens~ conditions *.
As described in FSAR Se.ction 1. 2.1 ar:ia~ showri on Figures 1. 2:...1 to l *2--8,
- the. Auxilia.ry Building and Service Wa*ter intake structures are th.e only structures housing safety related components and systems that are com-mon to both units.
In each c:ase, the sy:s;tems for Uni ts l and 2 are inde-pendent of each a.th.er and are located in different portions of the structures.
Th.e only shared system which is uti-lized in th~ safe shutdown of the plant is* the emergency control air
(
- I Regulation (10CFR)
GDC 10 G'DC 11 GDC 12 GDC 13 GDC 14.
M P80 89 01/36 Compliance supply which is described in FSAR Sectio*n 9.14.2.
FSAR Section 3.4.1 discusses the de-sign bases of the reactor core and Chapter 6 discusses the desi~~ bases of the ECCS.
These and the analyses of Chapter 14 assure that fuel design limits are not exceeded.
The core inherent reactivity feedback cha,racteristic*s and.reactivity con-trol methods are described in FSAR Section 3.3~1.2 and 3.3.1.3.
FSAR Section 3.3wl.6 describes the inherent and design features which eliminate or limit the various tY'pes of oscillations.
As descr.ibed in de.tail in Chapter 7, instrumentation and control systems have been p:r-0vided to monitor and maintain plant variables including
- tho*se variables* which affect the f is-sion process, integrity of the reac~
. tor core, the reactor coolant pres-*
sure b01:mdary, and the. containment, o.ve:r their prescribed ranges for normal. ope*ration~ anticipated occur-rences, and under accident con-ditions.
F:S;AR Chapter 4* discusses the reactor c:oolant pressure boundary and how it has been designed to accommodate the system temperatures and pressures at-tained under all e:xpected operational mods and anticipated transients, and to maintain stresses within applic-able limits *
(
- ~
'9'
~
- ~
Regulation (10CFR)
GDC 15 GDC 16 GDC 17 GElC 1.8 M P8*0 8 9 01/37 Compliance The design of the Reactor Coolant System to assure that the design mar-gins of the pressure boundary are not exceeded are described in FSAR Sec-tion 4.2.
The design bases of the ECCS and protection system are de-tailed in FSAR Sections 6.2 and 7.2, respectively.
As described in FSAR Sections 5.2.1,
- 5. 2 *. 2 and 5. 2 *. 3, a rein:torced con-crete, steel-lined containment struc-ture is provided.
It is designed to sustain, without loss of required i.ntegri ty, all e.ffe:ets of gross equipment failures, up* to an*..
including the rupture of the largest pipe. :l.n the Reactor Coolant System.
The containment and its. a.ssociated
- Eng.ineere.d Sa,f ety Fe.at.ures thus meet the requi.red function*al capability o.f this criterion..
As described in FSAR Sections 1 *. 2. 7 a'nd I. 2. 8*F, ohs*ite and offsi te power systems. are. provided which can inde~
. pendently supply the electric power required* *for th.e opera*tio.n of.. safety related systems.
This capability is maintained even w.ith the failure of any single active component in either syst.em.
Chapte*r 8 I ar10 SER Supple-ment 4,, page 872 provi.d.es the desi,gn details of* th.e pow.er systems and their compliance with this criterion.
The redundant e.lectric power systems important to s:af:ety are continuous*ly montiored and e.nergized during normal plan*t operation from redundant of.fsfte power sources.
Redundant
Regulation (10CFR)
GDC 19 GDC 20 GDC 21 M P80 89 01/38 Compliance onsite diesel generators provid~
automatic backup power sources.
Periodic tests of the diesel genera-tors, the transfer system and the station batteries are made, as re-quired by Technical Specifications.
Design details ~re provided in Chap-ter 8 of the FSAR and the Staff SER pag.e 8-2.
E'SAR Section 7. 7 describes the Main Control Ro.om, which contains the con-trols and ins*trumentation necessary for safe operation of the unit during.
normal and accident conditions.
Suf--
fu.cient shielding, distance, struc-tural integrity, and ventilation sys-tems are provided to ensure the con.:..
tro1 room.p.ersonnel will not re.ceive radiation exposures in excess of ~he criterion for the duration of the ac.-
cident.
In the event that access to t*he main control. room is restricted, auxiliary shutdown methods have. been provided., which may be used to main-tain the. reactor in a hot shutdown condition.
Subsequent cold s'hutdown may be achieve-a using suitable p.ro.cedures.
FSAR Se cti.ons 7. 2 and. 7. 5 d-iscus.ses the c:Iesign criteria and details of t.he protection system and engineere.d safety feature.s actua,tion, t*o show that the-req.uirenfents of thi,s c.ri te-rion are met.
As indiGa ted in FSAR Se.ct.ion 1. 3. 4, the protection system is designed.for t:iicg:h functional re:liability and inservice testabl i ty comme.nsurate
Regulation (10CFR)
GDC 22 GDC 23 GDC 25 M P80 89 01/39 Compliance with the safety functions to be per-formed.
The section, as well as Sec-tion 7.2, describe in detail the de-sign features provided to ensure re-dundancy and testability.
FSAR Section 7.2 describes how the protection system has been designed to provide suf£icient resistance to a broad class of acci.dent conditions or pos*tulated events.,
As indicated in FSAR Section L 3 *.4, the prote.c.tion system is designed wi.th due consideration of the most probable failure modes of th:e compo-nents under various perturbations of energy sou.rce.s. and the environment.
Further details are supplied in sec-tion 7.2.
FSAR Se.ct.ion 7 *. 2 discusses separation of th.e protection a.nd control sys-tems, such that the failure* of any single control system component or cha.nnel, or the failure or removal from service of a*ny protection system component or channe 1 wh.ich is *common to the protection and c*ontrol sys-tems, le.avesc inta:ct a system satisfy-ing all redundancy reliability, and independence requirements of th,e pro-tection system.
De.tails c.oncerning se:pa*r:ation of protection a:nd control systems a*re provided in Sectioris 7 *. 2
- 1. and 8
- 3
- 7
- FSAR Sections 3.3.1.4 and 7.2 indi-cate that the protection system he3,s been designed to assure that speci~
fied a:cc.eptable h1el design limits
Regulation (10CFR)
GDC 26 GDC 27 GDC 28 GDC 29 M P80 89 01/40 Compliance are not exceeded in the event of any single reactivity control system mal-function, including an accidental withdrawal of control cluster groups.
As indicated in FSAR Section 3.3.1.5, two independent reactivity control systems of different design prin-ciples are provided.
One of the sys-tems uses control rods; the second sys*tem employs dissolved boron as a chemical shim.
FSAR Section 14.1 discusses core pro-tection analyses including a mis-aligned road cluster control assembly.
FSAR Section 3.1.1.4 indicates that core reactivity is controlled by a chemical poison dissolved in the coolant, rod cluster assemblies and burnable poison rods.
The maximum reactivity inse.rtion relates due to withdrawal of a bank of rod cluster control assemblies or by boron dilu-tion ar limited.
The maximum worth of control rods and the maximum rates of reactivity insertion employing control rods are limited to values which prevent rupture of the coolant pressure boundary or disruption of the core internals to a degree which would impair core cooling capacity.
Further details are provided in Sec.-
tion 14.1.
FSAR Section 14.1 discusses the core protection analyses under a series of operational malfunction conditions.
The details of the design of the re-
Regulation (l.OCFR)
GDC 30 GDC 3.1 GDC 32 G:DC 3 3 GDC 34*
M P80 89 01/41 Compliance activity control, ECCS and protection systems are contained in Section 3.3, 6.2 and 7.2, and 7.3.
The design and testing of the reactor coolant system components are dis-cussed in FSAR Sections 4.2 and 4.5, respectively.
The code requirements of the various c.omponents are tabu-lated in FSA*R Table 4.1-12.
As indicated i.n FSAR response to Question 4.35, close control is main-ta-ine.d over materi.a1 selection and fabric.ation for* the. Reactor Coolant system to assure that the boundary behaves in a nonbrittle-manner.
FSAR Section 4. 5. 3 and Questions 4-. 6 and 4.29 discuss the de*sig.n of the-
- rea,ctor c*oo 1 ant sys tern with respect
- to inservice inspection.
Sec'ticm 4 ~5.1 discusses the reactor ve:s:s:el. inateri.al surveillance program.
As indicated in FSAR Section 6. 2,.. the Chemical and Volume Control System
- pro.v:icl:es a me:ans of reactor c*oolant make.up and adjus:tment ___ of the bo.ric acid concentration.
A high degree of functional re.liability and safe re-s;p_ons*e to prpbable modes of f.ai.lure is ass:ure.d by provision o.f standby components.
Details o*f system design are included* in Section 9. 2 and de-tails of the el.e.etrical power sys:tems a*l:"e g.ive:n in Chapter 8.
FSAR Section 6.2 indi.cates that the Re:sidual He.at Re.moval System, in
(
Regulation (10CFR)
GDC 35 GDC 36 M P80 89 01/42 Compl i.anc.e conjunction with the steam and power conversion system, is designed to transfer the fission product decay heat and other residual heat from th~
reactor core within acceptable limits.
Suitable redundancy is ac-complished below 350°F with the two residual heat removal pumps with means available for dra.ining and mon-itoring of: leakage, two heat* ex-changers, and the associated piping and cabl.ing.
The Residual Heat Re-moval System is able to operate on e:ither onsite or of:fsite ele.ctric*al power..
Sui table. redundancy above 350°F i.s provided by the steam gen-erators, a.uxiliary feed pumps, and attendant piping.
Details of the Re-s.idual He*at Removal System design are i.n FSAR Se.ction 9 *. 3.
FSAR Section 6. 2 de.scribes the use of F?as:sive a:ccumu.lators with two centri-*
!1.1gal. cha.rgin.g pumps and two low head safety* injection pumps to provide r~dundan.cy for failure of any compo-ne.nt in any system.
The primary function of the Emergency Core Cool-i.ng System is* to de.liver borated cooling water to the reactor cor.e in the* event of a loss-of-coolant-acci-eent..
This limits the fuel clad
. t.emperatl:lre and thereby ensures: that the core will remain* substanti.ally intact and in pla*ce, with its essen-tial heat transfer geometry pre-s*erved.
Tl::te inspectio.n program for the ECCS is discussed in FS'AR Section 6.2.5~
Period*ic inspe.ction requirements are
Regulation (10CFR)
GDC 37 GDC 38 M P80 89 01/43 Compliance included in the Technical Specif ica-t.ions.
FSAR Se.ction 6.2.5 indicates that the components of the Emergency Core Cooling System located outside the containment will be accessible for leak-tightnes.s inspection during ap-propriate periodic tests.
Each ac-tive componenet o.f the system may be individually a*ctuated on the normal.
power source at any time during plant opertation to demonstrate operabil-ity.
- The centrifugal charging pumps are part of the charging system, and this sy~tem is to continuous opera-tion during plant operation*.
Actua-tion c:ircuits. are tested and remote operated valves are exercised period-ically..
The test is described in de-tail in FSAR Section 6.2.5.2 and as per: Technical Specification su.rvei 1-lance requirements *.
As described in. FSAR Secti.ons 6. 3 a,nd:
6.4, adequate post accident heat removal c-a-pabil.ity is provided by t.wo se:parate' full capacity' engineered*
saf.ety features systems.
These are th.e containment spray system, whose.
components are described in Section 6.4 an~ the containment fan cooling system, whose components operated as d:escribe.d in Sect.ion 6. 3.
These.
systems are of d if.f.erent. engineering principles and serve as independent ba*ck.ups for each other.
Independent eTe.ctrical buses are connected to both onsite and offsite power.to feed the pump motors and the nece.ssary valves.
Regulation (10CFR)
GDC 39 GDC 40 GDC 41 GDC 42 GDC 43 M PBO 89 01/44 Compliance Section 5.5.5 of the FSAR describes the inspections of the containment ventilation system.
Further details for inspecting the containment heat removal systems are provided in Sec-tions 6.3.5.l and 6.4.4.1.
As described in FSAR Sections 6.3.5.2 and 6.4.4.2, provision has been made to allow testing the Containment Fan Cooling and Containment Spray Systems throughout the life of the unit to ensure that the systems are opera-tional.
Component testing, system testing and operational sequence testing are also described in these sections for both of the containment heat removal systems.
~s indicated by FSAR Section 5.3, systems are provided to control heat removal capability, radioactive con-tamination, gaseous iodine and par-ticulate radioactivity from the con-tainment atmosphere.
These systems are sufficiently redundant to meet the single failure criterion and are operable with either onsite or off-s i te power.
Sections 4.6.1.7 and 4.6.-2.3 of the Salem Unit 2 Technical Specifications describe the surveillance required on the containment atmosphere cleanup systems.
Additional discussions are provided in FSAR Section 5.5.S.
Section 5.5.S of the FSAR indicates that the containment ventilation sys-tems are designed to permit periodic
Regulation
{10CFR)
GDC 44 GDC 4~5 M P80 89 01/45 Cpmpliance pressure testinq and functional test-ing of the.ir components.
FSAR Section 9 *. 9 describes how all safety related items requiring cool-ing during an accident are cooled by the Service Water System.
Heat ex-changers requiring cooling during normal operation and c.ooldown are cooled e.ither by the. Component Coo.l-ing* System or the Service Water Sys-te,m..
The Service. Wa.ter System has sufficient redundancy to enable the.
system to meet the s*ingle *fa.ilure cri te*rion, including f'ailure of an emergency generator.
The Component Cooling System is provided with re-dundant pumping and heat transfer equipment and wil.1 operate with emer--
gency onsite power.
Discussion of these systems.is provided in FSAR Chap:te*r. 9
- As* i.nd:icat:ed in FS*AR sections 9 ~s a*nd 9*. 9;,. the, Se*rvi*ce *Water System and the C©mpon.ent Coo.ling System trans*fer heat f.rom structures, S¥Stems, and c0mponen.ts import:an t to safety to an ultimate he:at sink*.
Inspection of.
the portions o*f
- heaeer piping in the Service *water system is not practical since it is burie:d underground.
All
. rema*ining* piping., valves*, equipment, ama ass*0ciated el.ectrica.1 gear from the Service Water System can be in-spectee.
All piping, valves, equ.ip-It\\'ent,. and a.ss*ciciated electrical g.ear for the Componen.t Cooling Sys.tern can be inspected.
I
/
Re.gulation (10CFR)
GDC 46 GDC 50 GDC 51 GDC 52 GDC 53 M P80 89 01/46 Compliance FSAR Sections 9.5.4 and 9.9.4 discuss testing of the Component Cooling and Service Water Systems., respectively.
In addition, the T.echnical Specifica-tion detail periodic testing of sys-tem equipment.
FSAR Sections 5.1, 5.2 and 5.5 dis-cuss the design and test criteria for the Containment Bui.lding.
As discussed in FSAR Section 5. 2. 3,.
the design condition of the contain-ment pres:sure boundary is based on the parameters derived after the de..;.*.
sign basis accident.
For this design condition, the steel liner material behaves in a nonbri ttl.e manner and has the capabil.ity to minimize the pro,pagatio.n o*f* any undetected flaw.
Detai.led information _on the ste.el liner material is found in Se.ction 5 *. 2 *. 7~.6.
As i.ndic.ated in FSAR Section 5 *. 2.3(i), the* containment has been.
s:ubje.cted to an "one time only" air pressure test at 115 perc.ent de.sign pre:ssure.
Periodic integrated leak-ag*e rate tests. will be. performed as required by* 10CFR Appendix J, as -iin-pl~mented by the Technical Specif i-
. cat.ion.
FSAR Se.ction 5. 5 describes the con-tainment testing and inspection pro-gram.
Spe.cifically,. Section 5. 5 *. 3 dis:cus.ses penetration te*s:ts.
In a.d-di t.i.o.n, the requirements of* 1ocFRS O Appendix J a-re comm-i tted to in FSAR Se:ction 5. 5.
)
Regulation (10CFR)
G:OC 60
~ t..A.f"PAT'E:p IJ-Y Dr=:~er'V\\sE~ -1 o>
FR..orY\\
C:r DC M PS 0 8 9 0 1/ 4 7 Compliance As described in FSAR Chapter 5, the Containment Isolation System provides at least two barriers between the at-mosphere outside the containment structure and either the atmosphere inside the containment structure or the fluid inside the reactor coolant pressure boundary during accident c.onditions.
Operation of the Con-tainment Isolation System is automa.:..
tic.
- The failure of one barrier or a valve does not prevent isolation.
Means are provided to periodically test the sensor setpoints, the speed-
. of re:Sponse, the *ope:rability of fail:-
s:af e features, and the leakage rates of all. valves used for containment is:olation.
Furthe-r discussion is p:rovided in FSAR Section 5.4*.
Th.e* extent of complia,nce with Goe* 55, 5.6 and 57 is explained in FSAR _
qu:.e*stio:n responses 1.32 and 5 *. 19~
A-s desc.ribed in FSAR Ch-apter.Il, liquid, gaseous, and sol.id r-adioac-tive waste processing equipment is -
provided.. The prin.ciples of filtra-t-ie:n., - demineral.iz.at.ion, evapqration, soiidification and storag.e for decay are utiliz*ea* as de.scribe-cl in FSAR Cbapte-r 11..
Process monitoring is p-rovided to control this e.quipment iuad i::egi:llate. re-1.e*ase s
- to the environment as described in FSAR Chap.ter lL LlfT-re:it FRO""-
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- 57.
Regulation (10CFR)
GDC 61 GDC 62.
- <;:oc 63 M P8.0 8 9 01/4 8 Comp! ianc.e Various sections of the FSAR discuss how systems are designed to assure adequate safety while containing radioa.ctive materials.
Specifically, Reactor Coolant System -
Chap-ter 4 Containment -
Chapter 5 ECCS -
Chapter 6 CVCS -
Section 9. 2 RHR -* Section 9. 3 Spent Fuel Cooling - Section 9.4 Sampling - Sect ion 9
- 6 p*uel Handling - Section 9 *. 7 Auxiliary Building Ventilation -
Section 9.1 O Fuel Handling Ventilation -
Sec-tion 9.11 Waste Disposal Systems. -
Chap-te.r 11 The details of the d'.esi.gn of the Fuel Handl.ing and: Storag:e Systems are de.s*-*
cribed in FSA*R Section 9. 7.
FSAR Sections 1. 2 and 9. 7 shows the*
phys:i.cal a*rrangemen t* of the Fu.el Handling Building a*nd the relative
- . location of the Spent Fue.1 Pool and New F*uel s:torage pit, neither of which can be transversed by the Cask Hanel ing Crane.
P:SAR Ch.a:pters 9 and 11 des.cribe the monitoring capability in the fuel storag:e and waste handling areas.
Ope~Ci tors w,ill take approp.ria t.e actions if an alarm from any of these monitors is received.
Re.gula ti on (10CFR}
GDC 64 Appendix A Appendix B A-ppendi x C
- Appendix D M P80 8 9 01/ 4 9 Compliance FSAR Chapters 5 and 11 indicates that the facility contains means for monitoring the containment atmosphere and all other important areas during both normal and accident conditions to detect and measure radioactivity which could be released under any conditions.
The monitoring system includes area gamma monitors, atmos-pher.ic monitors and liquid monitors with indication in the control room.
Alarms* are provided to warn of high activity.
Section 11.2 discusses the proeess and area radiological moni-to-i;ing systems mohitor.ing prog.ram.
The En.vironmental Report and the Technical Specifications describe the off-site monitoring program.
Appendix D of the FSAR describes in detail the pr.ovisions of-th.e qual.i ty a-s:surance: program which has been im:..
plement:ed to meet all a-ppl.icable re'.""
quirements_of Appendix B.
This Appendix provides a guide for establishing the applicant's f ina*n-cial qua.li.fications.
PSE&G.'s finan-
- cial qua1.ification.s were reviewed by th:e RRC staff.
The Staff found that PSE&.G. had satis*fied the burden of proving that it ha*s rea.sonable asl?:urance* of having funds that it needs to o.perate the facility in compliance with the Commission **s re.g,1:1 lations.
This Appendix has been superseded by 10CFR part 51.
As noted in the dis-cussion for 10CFR50.40 (d}, the
(,,
Regulation (10CFR)
Appendix E Appendix F Appendix G and A*ppendix H M P80 89 01/50 Compliance reLevant applicable requirements of Part 51 have been satisfied.
This Appendix specif ices requirements for emergency plans.
An emergency plan was prepared for Salem 2, Units 1 and 2 prior to the granting of an operating license for Unit 1.
The Emergency Plans was previously re-viewed by the NRC as indicated in the Safe.ty Evaluation Report Supplement No. 3 which concluded that the emer-gency plans provided reasonable as-surance that appropirate measures can and will be taken in the event of an emergency to protect public health and safety and prevent damage to property.
The response to new criteria for emergency planning developed sub-sequent to the event at Three Mile I.s.land Unit 2, the emergency plan has been ~xtensively modified and im-proved.
The revised plan is develop-ed to meet the 6riteria of NUREG-06 54.
This Appendix applies to fuel repro-cessing plants and related waste man-ag.ernent facilities, not to power re-actors such as Salem 2, and it is therefore not applicable.
De*tail.ed information identifying the extent of conformance with Appendices G a.nd H of 10CFRSO is explained in FSA:R question response 4.35.
A request for exemption to Appendix G, paragraph IV.A.4 was filed on Febru-ary 12, 19 7 9.
f Regulati.on (10CFR)
Appendix I Appendix J M,.PBO 89 01/51 Compliance Th is Appendix provides numerical guides for design objectives and lim-iting conditions for operation to meet the criteria "as low as is rea-sona*bly achievable" for radioactive material in light-water-cooled nuc-lear pow-er reactor effluents.
The current Environmental Technical Spec-ification incorporates the provision of the concluding s:tatement of RMS0-2 w.hich provides numerical guides and limiting conditions for operation to assure that re.leases are as low as
- reasonable achievable.
As indicated in Supplement 2 t:o the-Safety Evalua-*
tion Report, the staff performed an
- independent evaluation of PSE&G' s ability to meet Appendix I to HlCFRSO, and concluded that the sys-tems installed at Salem w.ere capable of maintaining rel.eases of radioac-*
tive. material as low as is reasonable achievable.*
R;ea'cto*r containment leakage 'testing-for water cooled power reactors is delineated in this Appendix.
Tl:lese re.qµireme.nts are g*iven in Technical S*pe.c if ic.a ti.ans 3 I 4
- 6' *. 1. _2, 3 I 4 *. 6
- 1. 3 1<-
an*d 3/ 4. 6.1. 6.
Additional informa":'
ti.on con.cerning comp.liance can be found in FSAR Chapter 5. -
It s<l10.uld be noted that a spec.if ic e:xemption to th.is* Appendix has h>een granted in Te.chnical Speci.f ication 3/4.6.l.3 regarding testing of each centainment air lock
- I Regulation (10CFR)
Appendix K Appendix L Appendix M' A-ppendix N Appendix O Appendix P 1.o*o
- 1 lo:o.2 M P80 89 01/52 Compliance
- This Appendix specifies features of acceptable ECCS evaluation models.
As noted above for 50.4*6, the analy-sis for Salem 2 has been conducted using a model which has b~en accepted by the commission staff as meeting the requirements of this Appendix.
Th is Appendix cove.rs information re-que*sted by the Attorney General for an.ti-trust review of license a.pplica.-
tions.
This Appendix is not applic-able to Salem Un it 2.
This Appendix covers standardization o.f d:esign and is not a-pplicable to Salem 2 *.
Th, is Appendix covers s tandardi.zatio.n of *nu.clear power plant designs and. is not a*pplicable to Salem 2.
This -Appendix covers. standardiz.ation of de:s.i:gn
- a-rtd: is not applicable to s:a: Iem 2
- Th-is Appendix governs preapplication e:a*rl.y review of site suitability' is-s;u:es. and is not applicable to Salem
- i.
This regulation is expanatory and a.o~:s not impose independent obli.g:a,-
tfons on license.es.
'llhis re.gula.tion is self-explanatory.
S~alem 2 is not novel in design and is net. unproven or a prototype or pilot pla'nt
- _)
Re.gulation (10CFR) 100.3 100.10 100.11 Appendix A M PBO 89 01/53
-so-Compl i.ance This regualtion is explanatory and does no impose independent oblig a-t ions on licensees.
The factors listed related to both the unit design and the site have been provided in the application.
Site specifices, including seis-mology, meteorolgy, geology, and hydrology, are presented in Chapter 2 of the FSAR.
The exc-lusion a.rea, low-pop.ulation zone, and population -
center distance are provided and described.
The FSAR also describes-the characteristics of reactor d.esign _
and operation.
An exclusion are:a has been establish-ed, as de.scribed in FSAR Ch.apter 2.
The low population zone required by 100.11 (a) (2) has* be.en e-stablished,- -
a-s-aescribed in FSAR Section 2 *. 4. 5 as the area within a radial distance of
-- fiv.e ( 5) miles from the -:enter line of Unit Ne~ 1-and 2: containment build-ings..
As indicated in Section 2.4.4, the nearest population-center,_ a.s de:f in.ed by 10- CFR 100. 3 ( c), is Wilmington, Delaware, which is 18 mi le:s north of th.e site.
Tl:le FSAR accident analyses, parti c-u:lai:' those in*. Chapte-r 14 and F SAR Ap>F?endix r, demonstrate that off site d0ses resu1 t-ing from postulated acci-d'.ent.s would not exc.eed the cri te.ria in this section of the regula.tio:n.
Appendix A to 10 CFR Part 10*0 pro-vides seismic and geologic siting
-~-*' '
J
I.
I I
i i..
(-
' \\
Regulation (10CFR)
M PB*O 8 9 0 1/5 4 Compliance criteria for nuclear power plants.
The Commission determined that the saiem 2 site meets the NRC seismic and geologic siting criteria.
J