ML19338F653

Safety Evaluation Supporting Amend 3 to License DPR-75

ML19338F653
Person / Time
Site:	Salem
Issue date:	10/10/1980
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML19338F652	List: ML19338F651 ML19338F653 ML19338F654
References
NUDOCS 8010270016
Download: ML19338F653 (3)

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SAFETY EVALUATIONL 9

W na p' . _ f 8Y TIE OFFICE OF -NUCLEAR REACTOR REGULATION. <c Q-y- RELATE 04TO AMENDMENTsNO..3

• v T0 FACILITY.0PERATING-LICENSE NO.1DPR-75 9

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~ } PUBLICiSERVICE. ELECTRIC AND GAS COMPANY i m 4 m2 '). . SALEM GENERATING STATIGN, UNIT NO. 2

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s DOCKET NO:' 50-311' ~ .I ~ x- ~ j I .8y letters dated August 122; 1980', -Public Service Electric and Gas Company (the~ s ~ licensee)' submitted requests for an-amendment to their Facility Operating 9 I.icense DPR-75^ for Salen Generating Station Unit No. 2. The proposed technical- ' Specification' changes deal with the requirement to plug Row 1 tubesiin the steam 'a generators, changes-to the Salem Radiation Protection organization _and rewording 4I . of the' High Radiation. Area section. ~ JThe first request' is for removal of the requirements of Section 8.7 which E requires the111cansee to plug Row;1(tubes in the' steam generators prior to 9 ~ exceeding 5.' percent l power. The lic'ensee has requested.that the decision.to plug Row 1 tubes' be delayed unti1~ the'st'aff has evaluated the Westinghouse program lregarding Rowf1 tube? cracking.~ ;The^results are expected in. late November or. early December. Although thespotential for non-denting related Row'l tube crack-- . ing doesiexistfwethave concluded that for the reasons given below, operation 'of-

the' steam generators without Row 1 being plugged wil1 ~ not constitute an undue risk toithe health and l safety of. the"public:o The RowI ' tube leaks experienced to date at three operating plants have l

.1. .been small.and stable. c2.

Primary to secondarygleakage rate lisiits, and associated-surveillance i

requirements'will be established to/ provide assurance that the occurrence. 1 - / ^ of. tube cracking ~during operation will be datected and ' appropriate correc-2 tive action,isuch'asf tube: plugging, will: be taken such that any individual o crack present' will'not become unstable.under normal operating, transient d or accident conditions.. m.:"- f -In ' addition, the =11censee' has operated Salem, Unit.1 steam generators beyond the ~ ~n :first' refueling outage ~without~ experiencingL any leaking 'of Row 1 tubes. The idesign of Unitx2 steam generators:1s identical to.that.in Unit 1. 7 l X" y y+ ~ x

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The?1icensee has: proposed lsignificant' changes to the' Salem; Radiation P'rotection R

organization.E PSE86 changes; provide'for the separation ~of/the. radiation pro-- 5 itection; function from the-Perfomance Department'and formation of a new' Radia- ~ > < tion.' Protection Department. This new: department will'be headed by.a. Radiation P Protection Engineer who id11 report directly to the station Manager. It will l a have a Senior L pervisor - Radiation' Protection-(who'will:act as backup to the 1 H - M Radiatton Protection Engineer), Technical; Supervisors. Technicians.and Technical ~ Assistants Tall of.whos.will be devoted to the function of :adiation protection. !The remainder off the Performance Department will-be modified to split the Technical-Assistants:such:that1they are devoted to either the instrumentation - A - 7nd'controisifunction or the chemistry function'.- ,p These proposed changes meet lour positions inLthe draft " Criteria for Utility z E -Management and Technical Competence"1 and Regulatory Guide 8.8 as follows:

1. -

The Radiation.ProtecJon Engineer '(RPE - equivalent to the Radiation 1 4 2 Protection Manager) reports directly to the: Station Manager, independent.of -1 1 operational,' technic' l 'or adninistrative groups. The RPE is a required a P member.of. the Station Operations Review Committee (SORC). Staff qualifica-tions' ire that the RPE meet or exceed the recommendations of. Regulatory - 4 . Guide 1... q y ~ The' newly formed Radiation. Protection ' Department -has an independent U n i 2. radiation protection function at a11' levels,'and is separate fkm such func-i tions-as chemistry. A' backup'to the RPE, the Senior Supervisor-Radiation y

Protection has been designated. - All Technical Supervisors, Technicians-g

and Technical 1 Assistants within the department are devoted to the radiation protection. function.

aA ~ . A formal program to. replace contractor. radiation' protection personnel with 1 ' 3. ~ permanentlyJassigned ~ station radiation protection technicians has been~ Lisplemented. Additionally, a qualification and retraining program conducted - P 'in accordance with ANSI.18.1~, provides formal qualification.and training lfor the radiation protection department personnel. PSE8G anticipates the 5 2 M ' reorganization actions'and' programs to be fully complete by July 1, 1981. 'In the interim, a-permanent staff is.being recruited and all contractor a

radiation protection' technicians ~are receiving classroom and on the job' agf training onisystems, radiological fundamentals and procedures.

D 0 lThese actions and commitments by PSE8G for.the Salem Station adequately meet the q positions-of NUREGs-0660/0694 'NUREG-DRAFT " Criteria for Utility Management and yTechnicil Competence" and Regulatory Guide 8.8'regarding Radiation Protection + An evaluation of the Salem Radia-y(Organization:andarethereforesatisfactory.tionProtectionLDepartmentwill:be 4 gg k 7 g 7 6 ,s r^ 9 r 9 x }. ? ' ', { y Y..... l 4_~ ~ .j'c ?Q k b pf I xc 3 p g, "-{-

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M i f $%g,Q ; "W' ~ 4 b . M,J ' ~ _ ?.\\', m. m n,_ TM4.. s - ~?%:~% .3 t .x Ol, xTheffinal request concernsiSection 6.12 High'-Radiation Area. ~ The proposed. ~ ~ 'ETechnical Specification change'for,high radiation area 1 control provides adequate icontrols for avoiding unnecessary exposure by strictly controlling posting and e Barricades, High Radiation ~ Area posting, Radiation Exposure Permits, ,laccess. a dose rate' and dose monitoring. and11ocking where dose rates' exceed 1,000 milli- ~ ~ &a "[res/hr.:are utilized in the Standard.-Tech Spec. fomat for High Radiation Area ~ n:9 . control. This change adequately meets the-requirementv f 10 CFR?Part. o b' 'l20.203(c)(2)andtheALARAconsiderations'of:RegulatoryGuide8.8-andis n 1 acceptable.'- ~ t / Environmental Consideration- _gpr We have determined that thistaction-does not authorize a change in effluent types ~ ~ 'or. total l amounts nor' an' increase in power level and will not result in any signi- .ficant environmental impact.o Having made this determination

have further con-E

.cluded that.;this action isiinsignificant from the standpoint of environmental P-Limpact a'nd,: pursuant to:10 CFR 51.5(d)(4), that an environmental impact statementi ^ Lor' negative declaration'and environmental impact appraisal need not be prepared. ,p, ,-r onclusion. %3 We have concluded : based on the consideration discussed above, that: (1)' because

thej action does not' involve a

significant. increase in the probability or conse-

'T W' " ' Jguences of accidents previously considered and does not involve a significant: 1 " decrease in a safety margin,.the action:does not involveia significant hazards ~ consideration, (2) there is reasonable assurance that the health and safety of- ,the public will not bc endangered by operation in the proposed manner, rnd (3) such ' activities will be conducted in compliance with the Comission's regulations:- 5 and will not.be inimical to the common defense and security or to the health and P safety. of the public.; k I' GM O' M i 1 g., J

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