ML20080K999

Forwards Draft FSAR Changes to Resolve SER Open Issues 17 & 18 from Licensee Qualification Branch.Changes Will Be Incorporated in FSAR Rev Scheduled for Oct 1983

ML20080K999
Person / Time
Site:	Limerick
Issue date:	09/27/1983
From:	Bradley E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Schwencer A Office of Nuclear Reactor Regulation
References
RTR-NUREG-0991, RTR-NUREG-991 NUDOCS 8309300009
Download: ML20080K999 (27)

Text

_ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _.

e PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET l

P.O. BOX 8699 l

PHILADELPHI A. PA.19101 E

e AU ER. J R.

(215)8414000 a..e....a

..u s.,

EUGEN E J. BR ADLEY as.aceava enmanas counsak DON ALD BLANKEN RUDOLPH A. CHILLEMI E. C. KIR K H A LL T. H. M AM ER CORN ELL ggp y, ]%

PAUL AUERS ACH assesvant ess.amak counset EDW A RD J. CULLEN. JR.

THOM AS H. MILLER, J R.

G R ENE A. M.K EN N A asses? ANT COUNSEL Mr. A. Schwencer, Chief Docket Nos. 50-352 Licensing Branch No. 2 50-353 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Limerick Generating Station, Units 1 and 2 Safety Evaluation Report Open Issue Nos. 17 & 18 from NRC Licensee Qualification Branch (LQB)

Reference:

September 20, 1983 and September 21, 1983 Conference Calls between Philadelphia Electric and R. Benedict, NRC/LQB File:

GOVT l-1 (NRC)

Dear Mr. Schwencer:

Enclosed are draft FSAR changes developed as a result of the reference conference calls which we believe will resolve open review issue nos.17 and 18, as described in the Limerick Safety Evaluation Report (NUREG-0991).

We will incorporate these changes, exactly as they appear in the enclosures, in the FSAR revision scheduled for October,1983.

Sincerely, Euge e J.

ra ley 8309300009 830927 PDR ADOCK 05000352 E

PDR llDil/gra/G-4 I

l Copy to: See Attached Service List I

cc: Judge Lawrence Brenner (w/o enclosure)

Judge Richard F. Cole (w/o enclosure)

Judge Peter A. Morris (w/o enclosure)

Troy B. Conner, Jr., Esq.

(w/o enclosure)

Ann P. Hodgdon, Esq.

(w/o enclosure)

Mr. Frank R. Romano (w/o enclosure)

Mr. Robert L. Anthony (w/o enclosure)

Mr. Marvin I. Lewis (w/o enclosure)

Judith A. Dorsey, Esq.

(w/o enclosure)

Charles W. Elliott, Esq.

(w/o enclosure)

Jacqueline I. Ruttenberg (w/o enclosure)

Thomas Y. Au, Esq.

(w/o enclosure)

Mr. Thomas Gerusky (w/o enclosure)

Director, Pennsylvania Emergency Management Agency (w/o enclosure)

Mr. Steven P. Hershey (w/o enclosure)

Angus Love, Esq.

(w/o enclosure)

Mr. Joseph H. White, III (w/o enclosure)

David Wersan, Esq.

(w/o enclosure)

Robert J. Sugarman, Esq.

(w/o enclosure)

Martha W. Bush, Esq.

(w/o enclosure)

Spence W. Perry, Esq.

(w/o enclosure)

Atomic Safety and Licensing Appeal Board (w/o enclosure)

Atomic Safety and Licensing Board Panel (w/o enclosure)

Docket and Service Section (w/o enclosure)

(

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a LGS FSSR 3

.J This procedure shall also provide instructions to plant staff and operating personnel in areas of general and continuing applicability to plant management such as:

a.

The necessity to adhere to plant procedures and to refer directly to procedures for complex or extensive jobs where reliance on memory cannot be trusted, such as reactor startup, tasks that are infrequently performed, and complex tasks that must be performed in a specific order b.

The responsibility of plant personnel to take action, in the event of an emergency not covered by approved procedures, so as to minimize personnel injury and damage to the facility, and to protect public health and safety c.

Personnel conduct d.

Availability on call of plant staff and operating personnel e.

Preparation of plant logs and records f.

Requirements for shift turnover g.

Definition of "at the controls", per Figure 13.5-1 h.

Recording data or completing documentation as tasks are performed when such data or documentation of tasks is 1.

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J S R o Gdb) Pe B M,p F e 3.r-Z, r

13.5.1.4 Procedure for Release of Safety-Related Equipment This procedure shall implement the PEco standard requirements for blocking and tagging equipment and shall establish criteria for this function such as:

a.

Designation of personnel authorized to release equipment or systems for maintenance and the method of documenting such authorization b.

Aspects to be considered in releasing equipment such as:

how long equipment may be out of service; potential for degradation of protection when one subsystem of a redundant safety system has been removed from service; equipment and personnel safety c.

Aspects to be considered in returning equipment to service such as removal of jumpers and test signals and 28 to!f 3 i

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(1) only control panels associated with the ' operation of that unit or common unit panels are included inside the defined boundary.

If, in that future, panels are added to the control room, they are necessari1v included in the definition of "at the controls" for that unit. N ffice, ut111cy, or rest lacilities are not included in t t defined undary wit e

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o the unit 1 operator and the instrument lab and shop doors) a's_ Indicated.

FINAL SAFETY ANALYSIS REPORT (2)

Normal *at the controls" locations do not apply during any condition during which the control room is not habitable. In that event, the DEFINITION OF "at the control" location is the Emergency Shutdcwn panel for that unit.

"AT Ti1E CONTROLS"

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NOTES (1)

Only control panels associated with the operation of that unit or common unit panels are included inside the defined boundary.

in the future, panels are added to the control room, If, they are necessarily included in the definition of "at the controls" for that

unit, office, utility, or rest facilities are not included in the LIMERICK GENERATING STATION defir.ed boundary with the following h s exception /:

The unit 2 verbal cbmmunication as long as he remains in the office door, UNITS 1 AND 2 operator may open the Shif t Superintendent ~

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y-FINAL SAFETY ANALYSIS REPORT scribed bv the door and the_ door is held opeMsame situation pplies to the unit 1 operator ano as indicated.

instrument lab and shop doors, cne k

DEFINITION OF (2)

Notr.a1 "at the controls" locations do not apply during any condition

AT THE CONTROLS

during which the control room is not habitable.

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F 7.URE 13.5 1 SHEET 2 OF 2 j 1, 9/81 (3)

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ther are in the'futu panels are added to the control room, the contr ois~ ~th' t he essari.Jy included in the-deft 6IT1on of "at t

' ncluded ir1 define,,0f fice, utility;'Er restfollowing two exceptTIE The chit 2 unit.

facilities are r.o d beundary-sii'th the opc7ator maytpen the Shi't S<tferintendenf or adjacent of'ite dc or.

fort.wrb'El cc.munication as'long.ashe re:nains in fhe aret ci r ra-scribed by the door and M~r is held,jor' The ra.e s:tua*

applacs to the enit I cperator and the i

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Only control panels associated with the operation of that unit or con on unit panels are inc1cded inside the defined beandary.

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unit. Office, utility, or rest facilities are not included in the r^':

defined boundary with the follcwing > exceptiens:' wmay open the Shif t Superintendent or adjacent of fice[z-I oorS

-Mor verbal communication as long as he remains in the area circum-LIMERICK GENERATING STATION l

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S 1 AND 2 1 S R 0 scribed by the door and the door is held open.

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AWb e**r w b-NOTE Ly control t!.a t cnit or opmon unit jp nt}s associated with the operation of (1)

. neys are included inside the defined boundary.

If, i the fu re, p6ncIs are a a to the cont oom, they re n cessar' y ine uded in *.e dei nition o at

• e contr s for it it.

ffice, utilit er rest facilipf'es are not in s ude. i n.

h t4o except.cns: The ni N foll wing /endent or zdj efin bound.y wit f.e Si grir ent o 'i e acor, per tor may pen t'r' Shift for verbal c

.s.un' ation as 3 ng s he remain. i the a-c i r r tn-se ibed by

.e d. r anc the d is hcId open.

The same 5::ua: on unit 3 c;erator and the inst run n: lat. and t hois am,

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S hecedN er - $

LGS FSAR Such checklists or logs shall include any equipment under maintenance or test that by itself could degrade a system

\\/

critical to the prevention and mitigation of operational transients and accidents or initiate an operational transient (what to check and criteria for acceptable status shall be included on the checklist); and j

(3)

A' system shall be established to evaluate the effectiveness of the shift and relief turnover procedures (for example, i

periodic independent verification of system alignments).

]

Response

i The requirements stated in this section will be implemented except for the request to establish separate checklists or logs for use by the offgoing and ongoing auxiliary operators and maintenance technicians.

A variety of shift turnover checklists or logs, situated in various locations of the plant and under the control of many groups would further hinder the transfer of vital information to the operating shift personnel with primary responsibility for plant operations.

A limited number of checklists or logs, contralized in the control room and under the supervision of control room personnel, is essential to effective transfer of information.

Maintenance and testing of equipment vital to safe operation of the plant is performed with the knowledge and approval of the appropriate licensed control room operator.

The checklists, status boards, or logs will be utilized to identify any equipment under maintenance or test that by themselves could degrade a system critical to the prevention and mitigation of operational transients and accidents, or initiate an operational transient.

Some of this information will be supplied to the control room operators and supervisors, as appropriate, by the auxiliary operators and technicians for entry into the checklists and logs.

Shift personnel meetings under the direction of shift supervision are normally held shortly after shift turnover.

The euxiliery operatcr 's partk4pation-in these =eetir.gs -includes-revie of *ha

-check-lis ts-and -logs..

These methods are considered more effective in the transfer of vi 1 information during shift turnover than the use of separate lo n; by the auxiliary operators and technicians.

e I.C.3 SHIFT SUPERVISOR RESPONSIBILITIES This item is included ith Section I.A.1.2, Shift Supervisor Duties.

7

Response

F h sCRT 14' t o Rev. 26, pf/83 1.13-14 2

,.__.._,.-__,-~,,,,,,,,,__m.,......,y

e-I offgoing auxiliary operators will normally be relieved at their job locations in the plant, with a verbal report providing on-coming individuals with information (e.g., status of plant equipment and system alignment) on the past shif t significant activities and present operations in progress as related to the specific job position.

If plant conditions permit, the auxiliary operators would participate in the shif t personnel meetings and receive any additional information deemed necessary by shift supervision and control room operators.

f+

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• D uer n' e

proevoe --G 1

LGS ~FSAR 3

,13.1.2.17 Trainino Coordinator The Training Coordinator is responsible for establishing and implementing all facets of the station training program to meet the training requirements described in Section 13.2.

The Training Coordinator is responsible for developing the required training procedures to ensure that the training program is i

appropriately documented and that the fulfillment of training requirements is recorded.

13.1'.2.18 Succession of Authority During normal operation, the Station Superintendent is responsible for all station activities.

In his absence, the Assistant Station Superintendent assumes these responsibilities.

If both the Station Superintendent and the Assistant Station Superintendent are unavailable, absent, or incapacitated, the following persons, in the order listed, are responsible for all station activities:

a.

Technical Engineer b.

Operations Engineer l

13.1.2.19 Operatino Shift Crew The position titles, applicable operator licensing requirements, and minimum number of personnel.for each shift are described in Table 13.1-2 for the various combinations of units in either the operating or cold shutdown mode.

Six shifts provide 24-hours-per-day, 7-days-per-week operating coverage.

In addition to the above, Shift Technical Advisors (STAS) are assigned.

The STA is available to report promptly to the control room following a notification to perform the accident assessment 23vroer function during a plant transient.

The STA has no duties or responsibilities for manipulation of controls or command of Ntp r operations during the transient.

During a transient, the STA

)D*d.

observes control room instrumentation and, emergency core cooling system (ECCS) operation and availability to determine that the transient is proceeding as predicted.

The STA advises the shift superintendent of significant adverse conditions.

After a stable condition has been achieved, the STA aids shift personnel in j

SI 18 Rev. Jff,p5283 13.1-14

..e,

o s

Shift clerks will be provided to relieve Shift Supervision of many purely administrative duties which might interfere with their primary responsibility for the safe operation of the plant.

These activities may includes timekeeping, document control (procedures, drawings, instruction manuals), key issuance as directed by shif t supervision, and information input and retreival from various computers, i

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proper conduct of the radiation protection program and access to offsite management.

The Director - Radiation Protection Section j

also provides a means for ensuring that applicable experience gained at Limerick or Peach Bottom is reflected in the procedures and practices of both stations.

The Director - Radiation Protection Section meets the qualifications of

" engineer-in-charge" as defined in Section 4.6.1 of ANSI /ANS-3.1-1978 in regard to the support provided.

l The Nuclear Training Section is responsible for the training programs for licensed NRC operators (qualification and requalification), replacement training for licensed operators and senior operators, and non-licensed operations personnel and general employee training.

The section supervises, conducts, and keeps records of the necessary training.

The section is responsible for preparing and updating the training program.

4 13.1.1.1.2 Maintenance Division iN$6YLT {, ?Als FewA The Maintenance Division is under the direction of a Superintendent and is responsible for performing maintenance and repair work under the direction and coordination of the Maintenance Engineer on the plant operating staff.

Personnel in the Maintenance Division have the benefit of experience gained through years of providing maintenance support for Peach Bottom J

Atomic Power Station - Units 2 and 3.

13.1.1.2 Engineerino and Research Department i

The Engineering and Research Department is under the direction of the Vice-President.

The Vice-President is responsible for the establishment of policies directed toward the design, construction, and modification of Limerick Generating Station in j

accordance with applicable codes, standards, and regulations.

}

The Engineering and Research Department reviewed and approved material and component specifications, approved procurements, participated in or reviewed site-related engineering work and environmental studies, reviewed system designs, and participated in the monitoring and management of construction activities during the design and construction phase.

These design and engineering aspects are essentially complete.

2# to 13.1-3 Rev.)W,pt/83

)

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~

O 7 "S" O, ' ' 3 The Nuclear Safety Section, under the supervision of an Engineer-In-Charge, reports to the Superintendent-Nuclear Services on matters of a routine nature, and to the Chairman of the Operating and Safety Review Committee on matters of a safety-related nature.

The Section is responsible for independently examining the safety-related activities at the nuclear plants operated by the Philadelphia Electric Company, and providing support to the Operating and Safety Review Committee.

The Nuclear Safety Section consists of three groups:

a Corporate Independent Safety Engineering Group (ISEG),

an on-site ISEG at Limerick Generating Station, and an on-site ISEG at Peach Bottom Atomic Power Station.

The Engineer-In-Charge of the Nuclear Safety Section meets the qualifications of " engineer-in-charge" as defined in Section 4.6.1 of ANSI /ANS-3.1-1978 i

IM

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LGS FSAR C

TABLE 13.1-4 (Page 1 of 29)

ENGINEER-IN-CHARGE RESUMES i

Resumes for the following " Engineers-ir-Charge" are included, as identified in Section 13.1.1:

Electric Production Department / Generation Division-Nuclear (Section 13.1.1.1.1):

Engineer-in-Charge, Licensing Section l

En$ Cheer -i.w-Charf s, Nuclege S4fel Sect l,w

)

y Engineering and Research Department / Mechanical Engineering Division (Section 13.1.1.2.1)

Engineer-in-Charge, Nuclear and Environmental Section Engineer-in-Charge, Power Plant Design Section Engineer-in-Charge, Power Plant Services Section Engineer-in-Charge, Industrial Section Engineer-in-Charge, Civil Section Engineering and Research Department / Electrical Engineering Division (Section 13.1.1.2.2):

Engineer-in-Charge, Station Engineering Section Engineer-in-Charge, Electrical Equipment Section Engineer-in-Charge, Field Engineering Section Engineer-in-Charge, Computer & Controls Section Engineer-in-Charge, Transmission & Distribution Engineering Section Engineering and Research Department /Research and Testing Division (Section 13.1.1.2.3):

Engineer-in-Charge, Station Tests Section

~

25 to d

Rev. A, pf/83

L4c F:sM12-TABLE 13.1-4 (Cont'd)

Electric Production Department Nuclear Generation Division Engineer-In-Charge Nuclear Safety Section DATE APPOINTED:

February 1983 NAME:

George A. Hunger, Jr.

EDUCATION AND TRAINING:

1968 B.S of Mechanical Engineering - Lafayette College 1970 M.S. of Nuclear Engineering - University of Virginia 1981 Kepner-Tregoe Leadership Development Institute 1983 Management Oversight and Risk Tree Seminar WORK EXPERIENCE:

1970 to date Philadelphia Electric Company 1970 - 1975 Engineer - Research and Testing Division - Energy Conversion Research Section

- Involved in assessments of advanced nuclear concepts and participated on industry and Electric Power Research Institute review /research committees.

1973 - 1983 Alternate member of Peach Bottom Operation and Safety Review Committee 1974 - 1977 Instructor of Nuclear Engineering courses at Drexel University M Ef,loff3

1.1.5 F#F-Table 13.1-4 (Cont'd)

Page 2

i 1976 - 1980 Engineer - Mechanical Engineering Division -

Nuclear and Environmental Engineering Section

- Involved with Peach Bottom modifications and licensing activities and design review for Limerick.

1980 - 1982 Administrative Analyst - Corporate Planning &

Analysis Division - Involved with corporate studies, jointly-owned nuclear facilities management committee and taught management courses (Kepner-Tregoe).

1983 - Present Engineer-In-Charge, Nuclear Safety Section.

PROFESSIONAL ACTIVITIES:

Registered Professional Engineer in the Commonwealth of Pennsylvania Member of ANS - Past Chairman of ANS -

Delaware Valley Section Member of ASME L

SEV2T,(8[83

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TA3tf 13.I-5 Etecntae.

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& E*.J t?%,ATL O*J hytS400 Supena atteme T - Nuc,r_ag Se9.viC.Es TESUME m

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Mucles: Cent::tien 94"4 01 "upcrints..deuL MCC166s 3usvIcua DATE APPOINTED:

February 1983 NAME:

Werner T. Ullrich EDUCATION AND TRAINING:

1957 B.S. of Electrical Engineering - Drexel Institute of Technology 1960 Nuclear Engineering Course - Vitro Engineering EXPERIENCE:

1957 to date Philadelphia Electric Company 1957 - 1962 Engineer - Electrical Engineering Division -

Field Engineer - Involved post construction and initial energization testing of electric transmission lines, substations and controlled circuitry.

1962 - 1963 Engineer - Material Testing Reactor, National Reactor Testing Station, Idaho - Worked as a member of the operating shift, operating the reactor and experiments to gain experience in the nuclear fiald.

1963 - 1967 Shift Reactor Engineer - Peach Bottom Atomic Power Station - Worked in a shift supervisory capacity during the pre-operational testing, initial fuel loading, and start-up testing of the 40 MWe High Temperature Gas Cooled Reactor (HTGR).

Obtained NRC Senior Operator License for the HTGR in 1965.

1967 - 1968 Plant Engineer at Peach Bottom Atomic Power Station - Responsible for maintenance of HTGR as well as operator training.

.... ~

Pago 2

1968 - 1971 Assistant Station Superintendent, Peach Bottom Atomic Power Station - Responsible for operations of HTGR and development of organization and training programs for boiling water reactors in construction on the same site.

1969 Completed Observation Program at the General Electric Boiling Water Reactors Simulator at Dresden.

1971 - 1983 Station Superintendent, Peach Bottom Atomic Power Station - Responsible for the operation of the 40 MWe HTGR through 1975; the pre-operational testing, start-up and commercial operation of the two 1100 MWe boiling water reactors.

These units achieved commerical operation in 1975.

1983 to present Superintendent-Nuclear Services - Responsible for off-site support activities in the Nuclear Generation Divison for both Peach Bottom and Limerick.

This includes:

The Nuclear Safety Section; Emergency Preparedness Section; Licensing Section; Nuclear Training Section; and, Radiation Protection Section.

PROFESSIONAL ACTIVITIES:

Member of the American Nuclear Society -

Standard Operations Subcommittee (ANS-3) since 1978.

Assumed vice-Chairmanship of this committee, effective 1/1/81.

Member of the Board of Directors of the Institute of Nuclear Power Plant Operations since March 1981 - Fills one of the two positions assigned to individuals who have had recent experience in the management of an operating nuclear power plant.

ZseY.-7 lAJS E1 6 @, N E W#

LGS FSAR

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t may appoint, in writing (such as in Committee meeting minutes),

subcommittees for purposes such as performing reviews or studies in areas of particular expertise or for performing special investigations.

The O&SR Committee, and those performing reviews or audits under the cognizance of the Committee, shall have access to records and personnel as necessary to properly perform their functions.

The O&SR Committee shall be kept current on events within its responsibility by reviewing reports and by the activities of the Committee members.

The O&SR Committee shall hieet at least once every calendar quarter during the initial year of Unit 1 operation following fuel loading, and at least once every six months (or more often as determined by the chairman) thereafter.

A quorum shall consist of the chairman, or his designated alternate, and four members or alternates.

No more than a minority of the quorum shall have line responsibility for operation of the plant.

The O&SR Committee shall review:

a.

The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed

(

safety question.

b.

Proposed changes to procedures, equipment or systems that involve an unreviewed safety question as defined in 10 CFR Part 50.59 c.

Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR Part 50.59 d.

Proposed changes to technical specifications or the operating license prior to submittal to the NRC e.

Violations of codes, regulations, orders, technical specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

This shall normally be accomplished by review of PORC meeting minutes, special reports, or reports of audits.

f.

Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.

This shall normally be accomplished by review of PORC meeting minutes, special reports, or reports of audits.

% $I 30 Rev.[,JHf/83 13.4-4

T^'5EST @

n. /3. 4 -4 The O&SR consists of the following members and their alternates:

Members Alternate Manager-Electric Production, Superintendent-Nuclear Generation Chairman Division Vice President-Engineering &

Chief Design Engineer Research, Vice-Chairman Superintendent-Maintenance Superintendent-Electrical Section Division Maintenance Division Director-Environmental Affairs Chief Chemist Superintendent-Ouality Engineer-in-Charge - Quality Assurance Division Assurance Section - Engineering Electric Production and Research Chief Mechanical Engineer Engineer-in-Charge - Power Plant Design Section Director-Research and Testing Engineer-in-Cherge - Energy Conversion Research Section Chief Electrical Engineer Supervising Engineer-Plant Control Systems Chairman-Nuclear Review Board

• General Manager-Hope Creek

• Salem Generating Station Generating Station

• Employees of Ptablic Service Electric and Gas Company.

The members and alternates of the O&SR meet the qualifications of Section 4.7.2 of ANSI /ANS-3.1-1978.

The Chairman and Vice-Chairman of the O&SR meet the qualifications of Section 4.7.1 of ANSI /ANS-3.1-1978.

rsec. - g LGS FSAR c.

The corporate support group within the Nuclear Safety Section will screen external operating experience information and will send pertinent operating experience information to the Independent Safety Engineering Group (ISEG).

The ISEG will review this information and internal operating experience information, provide comments as appropriate, and distribute the information and the comments to the appropriate personnel

{

on plant staff.

If the ISEG determines that specific action should be taken at the plant, these recommended actions will be discussed with the appropriate personnel on plant staff and then submitted to the Engineer-In-Charge of the Nuclear Safety Section.

If during thA screening process by the corporate support group, operating experience information is determined to be urgent in nature, a copy of the operating experience information will be sent directly to the Plant Superintendent and the Operations Engineer, and the review by ISEG will be expedited.

Also, if any operating experience information is determined during the screening process or during ISEG review to need a broader interdisciplinary review, the information will also be sent to the Operating Experience Assessment Committee.

This Committee will consist of representation from ISEG, Plant Staff, Quality Assurance, Mechanical Engineering, and e

Electrical Engineering.

d.

Timely information regarding operating experience is now available to the company through the INPO Notepad System.

The corporate support group within the Nuclear Safety Section will review the Notepad items and forward applicable entries to the ISEG, Operations Engineer, and other plant and corporate personnel.

e.

The Administrative ProceOJre that will detail how operating experience is disseminated to the applicable organizations and persons within the plant staff will be written prior to fuel load.

However, dissemination of operating experience as described in item d, in particular Notepad items a~nd Licensee 1

Reports, is currently being done so that licensed operators and those to be licensed in the future are aware of operating i

events that are occurring within the industry.

This program will continue through the writing of the formal Administrative Procedure.

TWtACfi WM INS tSTLT

, 7Alat FotAowd

, <r 1

Rev.

p 83 630.32-2

tusetT Q N. 430 32-2.

Q 630.32

Response

C.

The Corporate Independent Safety Engineering Group (ISEG) within the Nuclear Safety Section will screen external operating experience information and will send pertinent operating experience information to the Limerick ISEG.

The Limerick ISEG will review this information and internal operating experience information, provide comments as appropriate and distribute the information and the comments to the appropriate personnel on plant staff.

If the Limerick ISEG determines that specific actions should be taken at the plant, these recommended actions will be discussed with the appropriate personnel on plant staff and then subr.itted to the Engineer-In-Charge of the Nuclear Safety Section.

If durin tha screening process by the Corporate ISEG, operati g experience information is determined to be urgen in nature, a copy of the operating experience info ation will be sent directly to the Station Sup rintendent, and the review by the Limerick ISEG will b

expedited.

Also, if any operating experience information is determined during the screening process or during Limerick ISEG review to need a broader interdisciplinary review, the information will also be sent to the Operating Experience Assessment Committee.

This Committee will consist of the Engineer-In-Charge of the Nuclear Safety Section, the Limerick and Peach Bottom Operations Engineers, representation from the Limerick ISEG, Quality Assurance, Mechanical Engineering, the Peach Bottom ISEG, Electrical Engineering and the Licensing Section.

d.

Timely information regarding operating experience is now available to the company through the INPO Notepad System.

The Corporate ISEG within the Nuclear Safety Section will review the Notepad items and forward applicable entries to the ISEG Station Superintendent Operations Engineer and other plant and corporate Limerick personnel.

f5ET, - 9 d

w LGS FSAR Information Letters and the Institute of Nuclear Power Operations Significant Operating Experience Reports d.

Track implementation status of significant corrective, action with regard to ISEG recommendations Provide onsite technical assistance, when required, to e.

assist in Limerick ISEG investigations f.

Provide an interface between the Limerick ISEG and Engineering and Research Department personnel, located in the corporate offices, who design plant modifications.

[TheOperatingExperienceAssessmentCommitteewillbecomposedof f

representatives from plant staff from both Limerick and Peach 2

Bottom, from ISEG groups at both Limerick and Peach Bottom, from Electric Production Department's Quality Assurance Division and from Engineering and Research Department's Mechanical Engineering and Electrical Engineering Divisions.

The committee members will receive, on a continuing basis, significant internal and external operating experience information, and will meet monthly to discuss it.

This committee will provide a broad interdisciplinary review and may make recommendations on improving operations, precedures, training, and maintenance.

1 This committee will facilitate the exchange of information on operating and design problems encountered at both Limerick and Peach Entta=

Also, because the Limerick and Peach Bottom plant designs are similar, many of the Peach Bottom ISEG's assessments particularly in the areas of design, training, correc,tive maintenance and, to some extent, operations, may be directly applicable to Limerick and vice versa.

The Peach Bottom ISEG will be similar in composition to and will have similar responsibilities as the Limerick ISEG.

j The Engineer-In-Charge of the Nuclear Safety Section reports to the Superintendent-Nuclear Services on matters of a routine i

l nature and to the Chairman of the Operating and Safety Review l

Committee on matters of a safety-related nature.

l i

"ii!CPLAC.E wIW W

.;%.,e r-u.ewwk Rev.J4,JdI/83 13.4-8

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y The Operating Experience Assessment Committee will be composed of the Operations Engineers from plant staff from both Limerick and Peach Bottom, engineers from ISEG groups at both Limerick and Peach Bottom, an engineer from Electric Production Department's Quality Assurance Division, an engineer from Electric Production Department's Licensing Section and engineers from Engineering and Research Departments's Mechanical Engineering and Electric Engineering Divisions.

The members will be degreed engineers that have, as a minimum, several years of nuclear plant operations or design experience.

The Chairman of the committee will be the Engineer-In-Charge of the Nuclear Safety Section.

The Vice-Chairman will be the Senior Engineer-Special Projects of the Licensing Section.

The committee members

~

will receive, on a continuing basis, significant internal and external operating experience information, and will meet monthly to discuss it.

This committtee will provide a broad inter-disciplinary review and may make recommendations on improving operations, procedures, training, and maintenance.

The ISEGs will inform the committee with results of their reviews of operating experience and operating problems.

This committee will facilitate the exchange of information on operating and design problema encountered at both Limerick and Peach Bottom.

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