ML20134Q148

Informs That NRC Staff Will Be Conducting Team Insp in Fire Protection at River Bend Station,Unit 1 Weeks of 970421 & 0505

ML20134Q148
Person / Time
Site:	River Bend
Issue date:	02/24/1997
From:	Wigginton D NRC (Affiliation Not Assigned)
To:	Mcgaha J ENTERGY OPERATIONS, INC.
References
NUDOCS 9702260285
Download: ML20134Q148 (5)

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m UNITED STATES

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R NUCLEAR RESULATORY COMMISSION 4

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WASHINGTON, D.C. *""' M February 24, 1997 i

j Mr. John R. McGaha, Jr.

Vice President - Operations Entergy Operations, Inc.

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River Bend Station l

P. O. Box 220

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St. Francisville, LA 70775 I

SUBJECT:

RIVER BEND STATION, UNIT 1 - NOTIFICATION OF CONDUCT OF A FIRE i

PROTECTION FUNCTIONAL INSPECTION (FPFI)

Dear Mr. McGaha:

f The purpose of this letter is to notify you that the U.S. Nuclear Regulatory l

Commission (NRC) staff will conduct a team inspection in the fire protection subject area at River Bend Station the weeks of April 21 and May 5, 1997. The i

Fire Protection Functional Inspection (FPFI) team will be lead by Mr. Patrick i

Madden, a senior fire protection engineer in the Office of Nuclear Reactor l

Regulation (NRR). The FPFI team will be composed of personnel from NRR, NRC Region IV, NRC Region II, and Brookhaven National Laboratory.

i The staff described the FPFI program in detail in SECY-96-267, " Fire Protection Functional Inspection Program," dated December 24, 1996. A copy of this paper is included for your information as Enclosure 1.

The FPFI procedure itself will be publicly available no later than mid-April 1997.

i The scope of this inspection is to review the implementation of your fire protection program.. The FPFI team will evaluate:

4 Fire Protection Program Administration i

Fire Protection Systems and Features i

Post-fire Safe Shutdown Capability and Implementation Fire Protection Configuration Management Program and Implementation Potential Fire Related Vulnerabilities Event Based Fires i

Fire Induced Plant Transients j

Seismic / fire Interaction In order for the staff to prepare for and perfom this comprehensive and j

complex inspection, members of the inspection team will visit River Bend Station on March 19 and 20, 1997. The purpose of this trip is to familiarize the team members with the River Bend Station, its fire protection program and its basis and to obtain program related information and documentation. The types of documents these team members will be interested in reviewing, and possibly obtaining, are listed in Enclosure 2.

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During the onsite inspection periods, we request that you ensure that copies i

of other analyses, evaluations or documentation regarding the implementation j

and maintenance of the River Bend station fire protection program, including post-fire safe shutdown capability, are readily accessible to the team gh f

I PDR ADOCK 05000458

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9702260285 970224 0

PDR I

o s-Mr. John R. McGaha, Jr.,

i their review. Of specific interest are those documents which establish that your fire protection program satisfies NRC regulatory requirements and conforms to applicable NRC fire protection guidance. Also, appropriate l

personnel, knowledgeable with. respect to those plant systems required to achieve and maintain safe shutdown conditions from inside and outside the control room (including the electrical aspects of the post-fire safe shutdown analyses), reactor plant fire protection systems, and the River Bend fire e

protection program and its implementation should be available at the site during the inspection.

i Approximately 2 weeks prior to the first week of the onsite inspection period, the inspection team plans to hold a conference call with cognizant members of 4

your staff to discuss administrative inspection details such as: office space i

size and location; specific documents requested to be made available to the team in their office spaces; arrangements for reactor site access (including j

radiation protection training, security, safety and fitness for duty requirements (to be discussed only if not resolved during the information j

gathering visit]); and the availability of knowledgeable plant engineering and licensing organization personnel to serve as points of contact and/or escorts during the inspection.

j Your cooperation and support during this= inspection will be appreciated.

If z

you have questions concerning this inspection or the inspection team's i

information or logistical needs, please contact Patrick N. Madden, the FPFI l

team leader, at 301-415-2854.

If you have questions regarding the FPFI program itself, please contact Leon WhKney, the FPFI Program Manager, at j

301-415-3081.

1 Sincerely,

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David L.

gginton, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-458

Enclosures:

1. SECY-96-267

2. Typical Fire Protection Program Supporting Documentation i

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Mr'. J hn R. McGaha,'Jr.' ;

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their review.

i

-Of specific interest are those documents which establish that your fire protection program satisfies NRC regulatory requirements and

. conforms to applicable NRC fire protection guidance. Also, appropriate-j personnel, knowledgeable with respect to.those-plant systems required to achieve and maintain. safe shutdown conditions from inside and outside the l

control room (including the. electrical aspects of the post-fire safe shutdown analyses) reactor plant. fire protection systems, and the River Bend fire protection program and'its implementation should be available at the site during the inspection.

l Approximately. 2 weeks prior to thel first week of the onsite inspection period,

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the Inspection team plans to hold a conference call with cognizant members of l

your staff to discuss administrative inspection details such as: office space j

size and location; specific documents requested to be made available to the

. team in their office spaces; arrangements for reactor site. access (including radiation protection training, security, safety and fitness for duty-requirements [to be discussed only if not resolved during the information

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gathering visit]);- and the availability of knowledgeable plant engineering and licensing organization personnel to serve as points of contact and/or escorts during the inspection.

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L Your cooperation and support'during this inspection will be appreciated.

If you have questions concerning this inspection or the inspection team's

.information or logistical needs, please contact Patrick M. Madden, the FPFI i

team leader, at 301-415-2854.

If you have questions regarding the FPFI program itself,l pleas'e; contact Leon Whitney, the FPFI Program Manager, at 301-415-3081.

l 4

u Sincerely, c

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- ORIGINAL SIGNED BY:

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~ David.L. Wigginton, Senior Project Manager n/>

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. Project Directorate IV-1 b

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' Divisiop of Reactor Projects III/IV-V,,y, 1

v. Office of Nuclear Reactor Regulation l

Docked",No.'50-458

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Enclosures:

J 1.'SECY-96-2'67)

2. Typical Fire Protection Program e

Supporting' Documentation DISTRIBUTION: Mittet fheh '

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Document Name: RBNDFPFI.LTR s*See previous concurrence 0FC FPFI TM LDR*

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(A)LA/PD4-1 NAME PMadden SWest DWhnon/vw CHawes0rn14 DATE-02/20/97 02/20/97

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OFFICIAL RECORD COPY G.

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i POLICY ISSUE i

December 24, 1996 SECY-96-267 f.QR:

The Commissioners

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f.B(ti:

James N. Taylor Executive Directer for Operations

SUBJECT:

FIRE PROTECTION FUNCTIONAL INSPECTION PROGRAN l

I PURPOSE:

To inform the Commission of the objectives, scope, and status of the new fire l

protection functional inspection program and of th." staff's plan to implement the program.

BACKGRDUND:

In a memorandum of August 25, 1992, the staff of the U.S. Nuclear Regulatory Commission (NRC) submitted to the Commission its action plan for resolving the Thermo-Lag fire barriers issues. The staff stated that it would develop and implement a program to inspect the Thenno-Lag corrective actions at each i

plant. At that time, the staff believed that the licensees would simply

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replace or upgrade their existing Thermo-Lag fire barriers. However, since i

that time, the licensees have proposed a much broader range of corrective i

action options. For example, many licensees have initiated fire barrier reduction programs. The objective of these programs, which are based largely on reassessments and subsequent revisions of the plant post-fire safe shutdown analysis, is to eliminate as much as possible the need for fire barriers.

Typical outcomes of barrier reduction programs include redefined fire area i

boundaries, new or relocated safe shutdown components, and new operator actions and procedures. Many licensees are also performing engineering l

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NOTE: TO BE MADE PGBLICLY AVAILABLE WHEN THE FINAL SRM IS MADE AVAILABLE CONTACTS:

1 i

Leon Whitney, NRR Steven West, NRR 301-415-3081 301-415-1220 i

1 ENCLOSURE 1

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l The Commissieners >

l evaluations to justify either eliminating certain Thermo-Lag barriers or l

keeping them as they are (i.e., without upgrades).

In some cases, the 2

i licensees have used such evaluations to justify exemptions from the NRC fire l

protection regulations, and we anticipate the trend to continue in the future.

l In the memorandum of August 25, 1992, the staff also informed the Commission i

that it would reassess the NRC reactor fire protection program to (1) determine if the program had appropriately addressed the safety issues, l

(2) detemine if licensees are maintaining compliance with the NRC fire l

protection requirements, (3) identify the strengths and weaknesses of the p ras, and (4) make recommendations for improvement. The staff issued its i

Report on the Reassessment of the NRC Fire Protection Program" on l

February 27,.1993. That report recosmonded, in part, that the staff Cl) develop a coordinated approach for the fire protection and systems inspections and (2) reevaluate the scope of the fire protection inspection program. In SECY-93-143, "NRC Staff Actions To Address the Recommendations in j

the Report on the Reassessment of the NRC Fire Protection Program" dated May 21, 1993, the staff infomed the Commission that it would implement these i

reassessment recommendations as part of the Fire Protection Task Action Plan.

To do so, the staff considered fire events, licensee reports of deficiencies in the fire protection program, previous NRC inspection findings, the scope and adequacy of the existing NRC fire protection inspection program, and the need to inspect other plant fire protection features in response to ongoing NRC programs (e.g., self-induced station blackout, fire barrier penetration seals, turbine building assessments, and individual plant evaluations of external events (IPEEEs)).

On the basis of the wide range of Thermo-Lag corrective actions proposed by the licensees, the staff concluded that an inspection of broader scope than that proposed in the Themo-Lag Action Plan was needed.

In addition, in view of the preliminary results of its work under the reassessment recommendation, the staff concluded that additional fire protection inspection effort appeared to be warranted.

In SECY-95-034, " Status of Recommendations Resulting from the Reassessment of the NRC Fire Protection Program," dated February 13, 1995, the staff informed the Commission that it was considering initiating a fire protection functional inspection (FPFI) program, which would cover all aspects of nuclear power plant fire safety (including Thermo-Lag fire barriers) and i

provide for more efficient, comprehensive and effective inspections. Revision and/or cancellation of some of the existing fire protection inspection 4

procedures will be considered as part of the FPFJ program.

In a memorandum to the Commission of September 20, 1995, the staff documented its conclusion that.an inspection of broader scope than that originally specified in the Thermo-Lag Action Plan was needed. The staff also informed the Commission that instead of the stand-alone Thermo-Lag fire barrier inspection program that it had proposed, it would develop and implement the FpFI program it had outlined in SECV-95-03' a February 8, 1996, the staff briefed the Chaiman on its plans for the wre direction of the NRC reactor fire protection program including the FPFI program. Later, in a memorandum to the Commission of April 3, 1996, the staff documented the framework for future direction of the NRC fire protection program with emphasis on the FPFI a,

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The Commissioners !

l program, a plan for developing and implementing this program, and a plan for i

centralized management, by the Office of Nuclear Reactor Regulation (NRR), of i

the FPFI program and all other reactor fire protection work.

l The staff presented its plans for the FPFI program to the Advisory Committee i

on Reactor Safeguards in March 1996. The staff also presented its plans to the nuclear industry at the Regulatory Information Conference of May 1996 and j

at the Nuclear Energy Institute fire protection forum of September 1996.

l DISCUSSION:

obiectives of the FPFI Proaram The FPFI program is a new headquarters-based inspection program. The program I

satisfies a number of objectives. The program satisfies staff plans to inspect Themo-Lag fire barrier corrective actions. The program also responds j

to the reassessment recommendation that the staff reevaluate the scope of the

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reactor fire protection inspection program and develop a coordinated approach j

for the fire protection and pos'.-fire safe shutdown systems inspections.

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this regard, the FPFI program will provide a strong, broad-based, and coherent inspection program that is commensurate with the safety significance of the subject and that will help ensure licensee compliance with NRC fire protection regulations and commitments. Benefits of the FPFI program include focusing l

NRC fire protection and support staff resources on the fire protection issues l

of most importance, (such as licensee control of the fire protection design and licensing bases), providing clear guidance to the staff and the nuclear i

industry regarding NRC oversight of licensee reactor fire protection programs, i

and improving the consistency of internal NRC oversight of the program. The i

program will also provide an immediate safety benefit arising from renewed industry attention to nuclear power plant fire safety.

Scene of FPFI Proaram i

The FPFIs will be announced inspections and will cover all aspects of plant fire safety. The staff will use risk insights to help focus the FPFIs on i

those areas most important to safety. The principal focus of the inspections i

will be on the plant fire protection and post-fire safe shutdown design and j-licensing bases and those fire protection program elements that are covered by l

existing NRC regulations and guidelines. These include, for example, safe i

shutdown perfomance objectives, safe shutdown systems and equipment, fire i

protection systems and barriers, emergency lighting, reactor coolant pump oil l

collection systems, quality control and quality assurance, configuration control including change control process, administrative controls and procedures, and training. This aspect of the FPFI program will satisfy the 4

program objective of ensuring continued licensee compliance with NRC fire protection regulations and commitments.

In addition, the pilot inspections will include a review of fire safety considerations that are not expressly addressed by the fire protection regulation, but by other regulatory programs.

This includes, principally, Generic Letter 88-20, Supplement 4, " Individual Plant Examinations of External Events (IPEEE) for Severe Accident Vulnerabilities,10 CFR 50.54(f)," June 28,1991. Such inspection areas

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The CommissiCners !.

I include, for example, event initiated fires, fire induced reactor transients, and potential seismic fire interactions. This feature of the FPFI program will provide useful information regarding brcader aspects of nuclear power 4

i plant fire safety. The staff will use this infomation to identify the i.

strengths and weaknesses of the overall NRC reactor firo protection program i

and to develop and support recommendations for program improvement, where l

appropriate.

The FPFI program consists of a pilot program followed by a permanent program.

The pilot program consists of four pilot inspections (one per region) i conducted in series over a 1-year period. The permanent p?ogram, as currently j

envisioned, would consist of four to eight NRC team inspections (one to two per region) ter year. 1.icensee self-assessments could also be an important I

element of tie permanent FPFI program. The staff will consider the role of self-assessments after it completes the pilot program.

A typical FPFI team will consist of a qualified team leader and four qualified 1

inspectors. The team leader will be a senior fire protection engineer or equivalent. The team will consist of a fire protection engineer, an electrical engineer, a plant systems engineer, and a regional inspector. A probabilistic risk assessment (PRA) specialist will help with inspection j

preparation by developing plant-specific risk-infomed infomation for the 1

inspection plan. The use of region-based inspectors will help maintain region office involvement in the program. The regional inspectors should have standard regional inspector qualifications. Experience in fire protection and plant systems inspections would be an advantage, but not required. The inspection activities that will be assigned to the regional inspectors will depend on their individual experience and qualifications. Specific inspection assignments will be made by the team leader as' part of inspection plan development. Examples include surveillance, testing, and repair activities and procedures; administrative controls; and quality assurance and quality controls.

For planning purposes, each FPFI will take 7 to 10 weeks (2 to 3 weeks to prepare, 2 weeks on site with a I week break between 1-week site visits, and 2 to 4 weeks to e @ the report). The first week of the onsite inspection will consist of a b6d-based hspection of the plant's overall fire protection and post-fire safe shutdown program. During the second week, the team will inspect areas of emphasis based on the results of the first week of the -

inspection. For example, if during the first week the team finds as part of the basic inspection program that the licensee has a weak configuration control program, the team could inspect this program in depth during the second week. The inspection team's findings wil be sufficiently developed to support enforcement actions, as appropriate. Enforcement actions will be processed by the regional offices witt the assistance of NRR and the Office of Enforcement (0E) in accordance with NUREG-1600, " General Statement of Policy and Procedures for NRC Enforcement Actions," and the "NRC Enforcement Nanual."

(Although the inspections will include review of fire safety considerations that are not expressly addressed by the fire protection regulation, as discussed above, infomation obtained from this aspect of the inspections should not lead to enforcement actions.) With respect to technical issues,

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The Commissioners j.-

i decisions regarding responsibility for follow up activities will be made on a case-by-case basis after the FPFI. The staff expects that in most cases, the regional offices will perfons the follow up activities. However, in some rare j

cases i', may be more appropriate or more efficient for NRR to follow up.

The FPFI procedure will be " modular" in that sections of the procedure that address discreu inspection topics could be conducted by individual inspectors independent of a full-scale FPFI. For example, under the Thermo-Lag Action Plan, the staff prepared a draft Thermo-Lag fire barrier inspection procedure.

This procedure will be converted into a fire barrier inspection procedure and integrated into the FPFI procedure. The staff could use this element of the FPFI program to inspect Thermo-Lag fire barriers independent of an FPFI, where appropriate. For example, it could be used at a plant that upgraded its j

Thorno-Lag fire barriers, but did not use the more complicated corrective action options discussed previously.

In general, the conduct of FPFIs will parallel that of other NRC team inspections. Before each inspection, the NRC team leader will assemble the inspection team, coordinate inspection preparation activities with the licensee and the individual team members, and prepare an inspection plan.

During the inspection, the team leader will manage the implementation of the inspection plan, manage the inspection team, and interface with the licensee.

After the inspection, the team leader will integrate the team member inputs into a compretensive NRC inspection report.

In addition, after each pilot inspection, the inspection team and appropriate NRC staff and management will critique the inspection and assess lessons learned. The staff will apply the results of the critiques and the lessons learned in the development of the inspection plan for the following pilot inspection.

After the four pilot inspections, the staff will reassess the lessons learned and modify the draft FPFI procedure and guidance to reflect the lessons learned. The revisions will be the final draft of the FPFI procedure and guidance. The staff estimates that it could complete this effort no later than 4 months after it completes the final pilot inspection. After the staff prepares the final draft FPFI procedure and guidance, it will conduct a public workshop regarding the FPFI program. During the workshop, the staff will discuss the FPFI program, present the results of the pilot program, and seek public and industry input. At this time, the staff will also consider the value of retaining those inspection elements that cover fire safety considerations that are not expressly addressed by the fire protection regulation. The staff estimates that it will conduct the workshop about one month after it completes the final draft of the FPFI procedure and guidance.

After the public workshop, the staff will finalize the FPFI procedure and guidance. At that time, the staff will also consider the need for training for additional FPFI ins >ectors. Depending on the extent of the comments and input received during tse workshop, the staff estimates that it will issue the final FPFI procedure and guidance 2 to 3 months after the workshop.

In addition, as part of its overall efforts to improve the effectiveness of NRC reactor fire protection inspections, the staff will reassess the existing core

1 The Commissioners -

fire protection inspection procedure (IP 64704, " Fire Protection Program") and develop recommendations regarding its future use or revision.

Current Status of FPFI Program Develonnent The Fire Protection Engineering Section of NRR will develop and implement the FPFI program. The staff is developing the FPFI procedure with technical assistance from Brookhaven National Laboratory and Scientech, Incorporated.

The staff has prepared a detailed outline of the FPFI program and procedures which have, in summary, the following major features:

use of risk insights (PRA and IPEEE, when available) first week (core or basic inspection elements)

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- fire protection design and licensing bases

- fire protection program i

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- post-fire safe shutdown capability l

second week (in-depth inspection elements) t l

- fire protection features, organization, controls, and practices j

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- post-fire safe shutdown implementation i

- configuration control and management

- event initiated fires l

- fire induced reactor transients

- seismic fire interaction i

enforcement actions, as appropriate inspection follow up activities, as needed i

e Using this outline, the staff has prepared an initial draft of the FPFI i

procedure and guidance. NRR and the regions have selected four pilot plants (one per region) using criteria such as: the magnitude and character of licensee Thermo-Lag corrective action programs, whether licensees have been proactive in implementing their fire protection programs, reactor plant fire protection enforcement history, and the strength of licensee configuration management programs. The NRR staff is working with regional offices to schedule the four pilot FPFI inspections. As discussed below, the staff plans to begin the pilot inspections during the first quarter of calendar-year 1997.

Intearation With other NRC Proarams j

In SECY-96-134, " Options for Pursuing Regulatory Improvement in Fire Protection Regulations for Nuclear Power Plants," dated June 21, 1996, the i

staff asked the Commission to approve an option for improving the fire protection regulations.

In a staff requirements memorandum of October 2, 1996, the Commission approved the staff recommendation to revise the current regulation. The Commission also stated that the staff should f

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consider such issues as inspection and enforcement in a manner consistent with

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that stated in the Commission's preliminary views on Direction Setting i

Issue 12 regarding risk-infomed, performance-based regulation. The staff l

will follow this direction.

In addition, the staff wi'l coordinate development of the FPFI program with the fire protection rulemaking effort.

l The staff will ensure that the FPFI procedure is appropriate for the current j

fire protection regulation and will update the procedure, as appropriate, when it revises the regulation.

lunact on Licensees l

Licensee support for an FPFI will be equivalent to that needed for other comprehensive team inspections. During inspection preparation, the licensee 4

j site and engineering organfrations wil' provide such information as results of l

licensee fire protection audits, reviews, and self-assessments; fire hazards i

analyses; post-fire safe shutdown analyses; design change control packages; j

procedures; and drawings. While the team is on-site, experienced and knowledgeable licensee personnel will be required to support the team's i

inspect'on activities. These personnel will coordinate answers to the t

inspectors' questions, and provide design drawings, plant procedures, and j

other documents as needed. The staff also expects that site engineering and licensing managers will participate in entrance and exit meetings.

i Mtc Staff Resource fanlications

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The staff will use headquarters and regional staff and technical assistance contractors to conduct the FPFIs. For planning purposes, the staff assumed 1

that each FPFI will take up to 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, about one full-time equivalent position. Additional staff time may be needed for inspection followup and enforcement activities depending on the inspection results. Resources are i

available to complete the pilot program described in this paper and to conduct i

up to four FPFIs per year as part of a permanent FPFI program.

If, at some l

time, the staff determines that it should conduct more than four inspections l

per year, it will revisit the resource implications.

t RECOMENDATION:

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The NRC staff will implement the FPFI pilot program described herein, unless l

directed otherwise by the Commission within 10 days from the date of this i

paper.

(The staff needs to schedule the first pilot inspection shortly so that it can be conducted no later than the first quarter of calendar j

year 1997.) The staff estimates that it can complete the pilot program within a year without adversely affecting other high-priority fire protection work.

l The staff will report to the Commission the results of the FPFI pilot program.

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.t-L The Commissioners j i

C00RDINATION:

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NRR is coordinating program development and inspection scheduling with the four regional offices and enforcement activities with OE.

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s or ecutive irector for Operations 1

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SECY NOTE: In the absence of instructions to the contrary, SECY will notify the staff on Monday, January 13, 1997 that the Commisrion, by negative consent, assents to the action proposed in this paper.

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DISTRIBUTION:

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OCAA OIG OPA OCA l

ACRS REGIONAL OFFICES 1

EDO SECY f

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Tynical Fire Protection Program Supportine Documentntion l

1.

The current version of the Fire Protection Program and Fire Hazards Analysis.

2.

Current versions of the fire protection program implementing procedures (e.g., administrative controls, surveillance testing, fire brigade).

3.

Fire brigade training program and pre-fire plans.

4.

Post-fire safe shutdown systems and separation analysis.

l 5.

Post-fire alternative shutdown analysis.

l 6.

Piping and instrumentation (flow) diagrams highlighting the components used to achieve and maintain hot standby and cold shutdown for fires outside the control room and those components used for those areas e

i requiring alternative shutdown capability.

i 7.

Plant layout and equipment drawings which identify the physical plant locations of hot standby and cold shutdown equipment.

i 8.

Color-coded,, marked-up electrical raceway drawings which identify the j

routing of power and control circuits for those plant systems necessary j

to achieve and maintain safe shutdown.

l 9.

Plant layout drawings which identify plant fire area delineation, areas protected by automatic fire suppression and detection, and the locations j

of fire protection equipment.

4 10.

Plant layout drawings which identify the general location of the post-fire emergency lighting units.

11. Associated circuit analysis performed to assure the shutdown functions and alternative shutdown capability are not prevented by hot shorts, shorts to ground, or open circuits (e.g., analysis of associated circuits for spurious equipment operations, common enclosure, common bus).

12. Plant operating procedures which would be used and describe shutdown from inside the control room with a postulated fire occurrir<g in any plant area outside the control room, procedures which would be used to implement alternative shutdown capability in the event of a fire in either the control or cable spreading room.

13. Maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, detectors, pumps and suppression systems.

14. Maintenance procedures which routinely verify fuse breaker coordination in accordance with the post-fire safe shutdown coordination analysis.

ENCLOSURE 2

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15. A sample of significant fire protection and post-fire safe shutdown related design change packages (including their associated 10 CFR 50.59 evaluations) and Generic Letter 86-10 evaluations.

16. The reactor plant's IPEEE, results of any post-IPEEE reviews, and listings of actions taken/ plant modifications conducted in response to 2

i IPEEE information.

17. Temporary modification procedures.

18. Organization charts of site personnel down to the level of fire j

protection staff personnel.

19.

If applicable, layout / arrangement drawings of potential reactor coolant / recirculation pump lube oil system leakage points and associated lube oil collection systems.

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