ML20147B800

Action Plans;Generic Communication & Compliance Activities

ML20147B800
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Issue date:	01/31/1997
From:	NRC (Affiliation Not Assigned)
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NUDOCS 9702030233
Download: ML20147B800 (106)

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DIRECTOR'S STATUS REPORT l

on GENERIC ACTIVITIES Action Plans  !

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Generic Communication and 1 Compliance Activities JANUARY 1997 Office of is c, aar Reactor Regulation Ala 888 Hal 2 PDR

INTRODUCTION

, The purpose of this report is to provide information about generic activities, including generic communications, under the cognizance of the Office of Nuclear Reactor Regulation. This report, which focuses on compliance activities, complemente NUREG-0933, "A Prioritization of Generic

Safety issues."

j This report includes two attachments: 1) action plans and 2) generic communications under development and other generic compliance activities. Generic communications and compliance activities (GCCAs) are potential generic issues that are safety significant, require technical resolution, and possibly require generic communication or action.

4 Attachment 1, "NRR Action Plans," includes generic or potentially generic issues of sufficient complexity or scope that require substantial NRC staff resources. The issues covered by action

,j plans include concerns identified through review of operating experience (e.g. Boiling Water

Reactor Internals Cracking and Thermolag), and issues related to regulatory flexibility and improvements (e.g. New Source Term and Probabilistic Risk Assessment (PRA) Implementation Plan). For each action plan, the report includes a description of the issue, key milestones, discussion of its regulatory significance, current status, and names of cognizant staff.

4 Attachment 2, " Generic Communications and Compliance Activities," consists of three monthly 4 status reports.1) open GCCAs, 2) GCCAs added since the previous report, and 3) GCCAs closed j since the previous report. The generic communications listed in the attachment includes bulletins, i generic letters, and information notices. Compliance activities listed in the attachment do not rise i to the level of complexity that require an action plan, and a generic communication is not currently scheduled. For each GCCA, there is a short description of the issue, scheduled completion date,

< and name of cognizant staff.

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Attachment 1 1

NRR ACTION PLANS 1

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, TABLE OF CONTENTS 1

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! BOILING WATER REACTOR INTERNALS CRACKING ............. 1 MOTOR-OPERATED VALVES ACTION PLAN . . . . . . . . . . . . . . . . . . . 4 l STRUCTURE ACTION PLAN ............................... 7 DRCH j UPDATE OF SRP CHAPTER 7 TO INCORPORATE DIGITAL J

INSTRUMENTATION AND CONTROLS (l&C) GUIDANCE . . . . . . . . 10 l GRADED QUALITY ASSURANCE ACTION PLAN ................ 12 4

DRPM NEW SOURCE TERM FOR OPERATING REACTORS .............. 17 ENDANGERED SPECIES ACTION PLAN . . . . . . . . . . . . . . . . . . . . . . . 20 i

' ENVIRONMENTAL SRP REVISION ACTION PLAN . . . . . . . . . . . . . . . . 22 10 CFR 50.59 ACTION PLAN DEVELOPMENT . . . . . . . . . . . . . . . . . . 24 INDUSTRY DEREGULATION AND UTILITY RESTRUCTURING . . . . . . . . 27 1

i DnPW GENERAL ELECTRIC EXTENDED POWER UPRATE ACTION PLAN . . . . . 30 DRY CASK STORAGE ACTION PLAN ....................... 32 j DSSA ACCIDENT MANAGEMENT IMPLEMENTATION . . . . . . . . . . . . . . . . . 35

! FIRE PROTECTION TASK ACTION PLAN . . . . . . . . . . . . . . . . . . . . . . 38 i PRA IMPLEMENTATION ACTION PLAN ................... .. 40 l i ENVIRONMENTAL QUALIFICATION TASK ACTION PLAN . . . . . . . . . . 45 CORE PERFORMANCE ACTION PLAN . . . . . . . . . . . . . . . . . . . . . . . . 47

! HIGH BURNUP FUEL ACTION PLAN . . . . . . . . . . . . . . . . . . . . . . . . . 50 WOLF CREEK DRAINDOWN EVENT ACTION PLAN 52

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BOILING WATER REACTOR INTERNALS

TAC Nos. M91898, M93925, M93926, M93627, Last Update: 12/19/96 i M94959, M94975, M95369, M96219, Lead NRR Division: DE

M96539 Supporting Division

DSSA GSI: Not Available i

! MILESTONES DATE (T/C)

PART 1: REVIEW OF GENERIC INSPECTION AND EVALUATION CRITERIA j 1. Issue summary NUREG-1544 03/96 C

. 2. Review BWRVlP Re-inspection and Evaluation Criteria

o Reactor Pressure Vessel and Internals Examination Guidelines (BWRVIP-03) 03/97 T o BWRVIP-03, Section 6A, Standards for Visual Inspection of Core

Spray Piping, Spargers, and Associated Components o BWR Vessel Shell Weld Inspection Recommendations 03/97 T (BWRVIP-05) o Guidelines for Reinspection of BWR Core Shrouds (BWRVIP-07) '

03/97 T

3. Review of generic repair technology, criteria and guidance TBD

4. Review generic mitigation guidelines and criteria TBD

5. Review of generic NDE technologies developed for examinations of TBD l BWR internal components and attachments '

6. Other internals reviews (safety assessments, evaluations, mitigation measures, inspections and repairs) o Safety Assessment of BWR Reactor Internals (BWRVIP-06) I o Evaluation of Crack Growth in BWR Stainless Steel RPV Internals I (BWRVIP-14) 06/97 T o Roll / Expansion of Control Rod Drive and in-Core Instrument Penetrations in BWR Vessels (BWRVIP-17) 06/97 T l o BWR Core Spray Internals inspection and Flaw Evaluation l Guidelines (BWRVIP 18) 09/97 T l o Internal Core Spray Piping and Sparger Repair Design Criteria I (BWRVIP-19) 03/97 T I 04/97 T l

i By letter dated September 20,1996, the BWRVIP informed the staff of its l intention to Petition for Rulemaking to change the augmented inspection I requirements contained in 10 CFR 50.55a(g)(6)(ii)(A), in accordance with the recommendations of BWRVIP-05. RES would have the lead for review of the rulemaking petition. J 1

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Descriotiom Many components inside boiling water reactor (BWR) vessels (i.e., intamals) are made of materials such as stainless steel and various alloys that are susceptible to corrosion and cracking. This degradation can be accelerated by stresses from temperature and pressure changes, j chemical interactions, irradiation, and other corrosive environments. This action plan is intended to <

encompass the evaluation and resolution of issues associated with intergranular stress corrosion cracking (IGSCC) in BWR intomals. This includes plant specific rr. views and the assessment of the j generic criteria that have been proposed by the BW.1 Owners Group and the BWRVIP technical  !

subcommittees to address IGSCC i1 core shrouds and other B%TI internals. l Historical Backaround: Significant cracking of the core shroud was first observed at Brunswick, Unit 1 nuclear power plant in September 1993. The NRC notified licensees of Brunswick's discovery of significant circumferential cracking of the core shroud welds. In 1994, core shroud i cracking continued to be the most significant of reported internals cracking. In July 1994, the NRC '

4 issued Generic Letter 94-03 which requires licensees to inspect their shrouds and provide an analysis justifying continued operation until inspections cai be completed.

A special industry review group (Boiling Water Reactor Vessels and Internals Project-BWRVIP) was ,

formed to focus on resolution of reactor vessel and internals degradation. This group was  ;

instrumental in facilitating licensee responses to NRC's Generic Letter. The NRC evaluated the review group's reports, submitted in 1994 and early 1995, and all plant responses.

All of the plants evaluated have been able to demonstrate continued safe operation untilinspection or repair on the basis of: 1) no 360* through-wall cracking observed to date, 2) low frequency of pipe breaks, and 3) short period of operation (2-6 months) before all of the highly susceptible plants complete repairs of or inspections to their core shrouds, in late 1984, extensive cracking was discovered in the top guide and core plate rings of a foreign i reactor. The design is similar to General Electric (GE) reactors in the U.S., however, there have '

been no observations of such cracking in U.S. plants. GE concluded that it was reasonable to i

- expect that the ring cracking could occur in GE BWRs with operating time greater than 13 years.

In the special industry review group's report, that was issued in January 1995, ring cracking was evaluated. The NRC concluded that the BWRVIP's assessment was acceptable and that top guide ring and core plate ring cracking is not a short term safety issue.

Erooosed Actics.s: The staff will continue to assess the scopes that have yet to be submitted by  ;

licensees concerning inspections or re-inspections of their core shrouds. The staff will also continue to assess core shroud inspection results and any appropriate core shroud repair designs on a case-by-case basis. The staff willissue separate safety evaluations regarding the acceptability of core shroud inspection results and core shroud repair designs. The staff has been interacting with the BWRVIP and individual licensees. In an effort to lower the number of industry and staff resources that will be needed in the future, it is important for the staff to continue interacting with the industry on a generic basis in order to encourage them to continue their proactive efforts to j resolve IGSCC of BWR internals. The BWRVIP has submitted ten generic documents, supporting 3

plant specific submittals, for staff review. The staff is ensuring that the generic reviews are incorporating recent operating experience on all BWR internals.

Oria:natina Documenp Generic Letter 94-03, issued July 25,1994, which requested BWR 1 licensees to inspect their core shrouds by the next outage and to justify continued safe operation l until inspections can be completed.

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Ranulatnry Assessment: In July 1994, the NAC issued Generic Letter 94-03 which required licensees to inspect their shrouds and provide an analysis justifying continued operation until inspections could be performed. The staff has concluded in all cases that licensees have provided sufficient evidence to support continued operation of their BWR units to the refueling outages in which shroud inspections or repairs have been schedu:ed. In addition, in October 1995, industry's special review group submitted a safety assessment of postulated cracking in all BWR reactor internals and attachments to assure continuing safe operation.

Current Status: Almost all BWRs completed inspections or repairs of core shrouds during refueling outages in the fall of 1995. Various repair methods have been used to provide alternate load carrying capability, including preemptive repairs, installation of a series of clamps and use of a series of tie-rod assembibs. The NRC has reviewed and approved all shroud modification proposals that have been submitted by BWR licensees. Review by NRC continues on individual hspection results and plant-specific assessments.

In October 1995, industry's special review group issued a report (BWRVIP 06) which the NRC staff's preliminary review indicates was not comprehensive. The NRC staff has sent a request for additional information. The NRC staff is still awaiting the RAl response, which the BWRVIP has stated in several telephone calls to be imminent, in addition, the industry group submitted a report on reinspection of repaired and non-repaired core shrouds (BWRVIP-07) in February 1996. The staff is currently reviewing both this report and the supplemental :nfortnation provided in the BWRVIP's response to the NRC staff's request for additional !nformation. The NRC is also reviewing laformation submitted by GE on the safety significance of and recommended inspections for top guide and core plate ring cracking. Review of the " Reactor Pressure Vessel and Intemals Examination Guidelines (BWRVIP-03)* has slipped to allow for reviaw by NRC contractor. By letter dated September 20,1996, the BWRVIP informed the staff of its intention to Petition for Rulemaking to change the augmented inspection requirements contained in 10 CFR 50.55alg)(6)(ii)(A), in accordance with the recommendations of BWRVIP-05.

1 NRR Technical Contacts: David Terao, EMCB, 415-3317 ,

Merrilee Banic, EMCB, 415-2771 Kerri Kavanagh, SRXB, 415-3743 Frank Grubelich, EMEB 415 2784 ,

NRR Lead PM: C. E. Carpenter, EMCB, 415-2169 j

References:

Generic Letter 94 03, "Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors," July 25,1994 Action Plan dated April 1995 l

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l MOTOR-OPERATED VALVES ACTION PLAN

, TAC Nos.M80330, M82072, Last Update: 12/27/96

! M75089, M88898 Lead NRR Division: DE a

MILESTONES DATE l (T/C)

, Regulatory improvements: 1/96-9/96 (C)

(1) Staff is working with ASME to improve the inservice testing j requirements in the ASME Code and (2) Staff is working with OM j to develop guidelines for periodic verification of MOV design-basis capability to replace stroke-time testing.

! New Generic Letter on MOV Peziodic Verification:

} Staff preparing generic letter to provide recommendations on the periodic verification of MOV design-basis capability.

i j lssae for public comment 2/96 (C) l Final issuance 9/96 (C) l

! I MOV Inspection Module: the staff will prepare an inspection 6/97 (T) )

module for inspecting MOV programs over the long-term and provide appropriate training for inspectors. I Review of EPRI MOV Performance Prediction Program: NRR and RES are currently reviewing a topical report submitted by NEl on the EPRI MOV Performance Prediction Program.

SER 2/96 (C)

SER SUPPLEMENT 1/97 (T)

DescriotioD: Appendices A and B to 10 CFR Part 50 and 10CFR50.55(a) require nuclear power plant licensees to establish programs to ensure that structures, systems, and components important to the safe operation of the plant are designed, installed, tested, operated, and maintained in a manner that provides assurance of their ability to perform their safety functions.

GL 8910 and its supplements, asked licensees to help ensure the capability of MOVs in safety-related systems by reviewing MOV design bases, verifying MOV switch settir.gs initially and periodically, testing MOVs under design-basis conditions where practicable, improving evaluations of MOV failures and necessary corrective action, and looking for trends in MOV problems. EMEB has programmatic oversight responsibility of regionalinspection activities conducted to verify that licensee MOV programs are being implemented. EMEB provides support to the regions, either by staff or contractor expertise, for the conduct of inspections in this area and closure of licensee actions pursuant to GL 8910.

Historical Backaround: In 1985, the Davis-Besse nuclear power plant experienced a total loss of feedwater when, following a loss of main feedwater, safety-related MOVs in the auxiliary feedwater system could not be reopened after their inadvertent closure. As a result of this and other information, the NRC staff issued Bulletin 85-03 (November 15,1985) requesting that licensees verify the design-basis capability of safety-related MOVs used in high pressure systems.

The information from the implementation of Bulletin 85-03, additional operating events, and NRC-4

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sponsored research indicated the need to expand the scope of Bulletin 85-03 to all safety-related i systems.

2 j in Generic Letter (GL) 89-10 (June 28,1989) and its supplements, the NRC staff asked licensees to help ensure the capability of MOVs in safety-related systems by reviewing MOV design bases, j verifying MOV switch settings initially and periodically, testing MOVs under design-basis conditions 4

where practicable, improving evaluations of MOV failures and implementing necessary corrective action, and looking for trends in MOV problems. The NRC staff requested that licensees complete 2

the verification of the design-basis capability of MOVs included in the scope of GL 89-10 within three refueling outages or five years from the date of issuance of the generic letter, whichever was

, later. The NRC staff has issued seven supplements to GL 89-10 that provide additional guidance -

i and information on GL 89-10 program scope, design-basis reviews, switch settings, testing, j periodic verification, trending, and schedule extensions.

i In June 1990, the NRC staff issued NUREG-1352, " Action Plans for Motor-Operated Valves and l Check Valves," describing actions to organize the activities aimed at resolving the concerns about

the performance of MOVs and check valves. These actions included evaluating the current

regulatory requirements and guidance for MOVs, preparing guidance for and coordinating NRC j inspections, completing NRC MOV research programs and implementing the research results, and j providing the nuclear industry with information on MOVs.

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Proposed Actions

Specific activities included in the generic action plan to improve MOV i performance are:

(1) Regulatory improvements - The staff is working with ASME to improve the inservice testing l requirements in the ASME Code and the staff is working with OM to develop guidelines for periodic verification of MOV design-basis capability to replace stroke-time testing. Recently, ASME issued

Code Case OMN-1, " Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor

. Operated Valve Assemblies in LWR Power Plants JM - Code - 1995 Edition: Subsection ISTC,"

j which is contained in OMa 1996 Addenda to %e 1995 C&M Code. The staff references the code case in recently issued Generic Letter 96-05. ASME will consider incorporating the code case into the ASME Code in the future. This milestone is considered to be complete.

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j (2) EPRI MOV Performance Prediction Program - Or. March 15,1996, the staff issued the Safety Evaluation on the topical report on EP31 MOV Performance Prediction Program. The staff is j reviewing the hand-calculation models tw two unique gate valve designs.

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l (3) MOV Periodic Verification Generic Lettet - The staff prepared a generic letter to provide

recommendations on the periodic verification of MOV design-basis capabllity. On September 18,

, 1996, the staff issued GL 96-05, " Periodic Verification of Design-Basis Capability of Gafety-Related i Motor-Operated Valves."

(4) MOV Inspection Module - The staff plans to prepare an inspection module for inspecting MOV programs over the long-term and provide appropriate training for inspectors.

Oriainatina Document: NRC Bulletin 85 03 issueJ November 15,1985.

Reaulatorv Assessment: While it is important for the licensea to take steps to ensure that MOVs

! will operate reliably under design-basis conditions, the probability of any individual MOV failure is

{ small and safety systems are robust enough to provide reasonable assurance of public health and j safety.

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Current Status: Coordination with industry and support to NRC regional staff, efforts on codes and standards, and MOV research and analysis are ongoing activities. On September 18,1996, the staff issued GL 96-05, " Periodic Verification of Design Basis Capability of Safety-Related Motor-Operated Valves."

On March 15,1993, the staff issued a non-proprietary Safety Evaluation on the EPRI MOV Performance Prediction Program. The staff is reviewing the remaining EPRI models for two unique gate valve designs and plans to issue a supplement to the SE r.ddressing these two models later in 1996. The staff has been alerting licensees, NEl and EPRI to the staff's findings from the EPRI program review, and has been communicating staff views with industry regarding periodic verification. On August 21,1996, the staff issued Information Notice 96-48 to alert licensees to lessons learned from the EPRI MOV program. In addition, the staff has been factoring the overall findings from the EPRI program into staff activities.

With the issuance of Generic Letter 96-05, EMEB is working to complete the supplement to the SE on the EPRI MOV Topical Report before closing the MOV Action Plan and will completc the remaining tasks as part of the implementation phase of the generic letter.

NRR Technical

Contact:

Thomas G. Scarbrough, EMEB, 415-2794 NRR Lead PM: Allen G. Hansen, DRPW, 415-1390 References.:

Bulletin 85-03, November 15,1985 Generic Letter 89-10, June 28,1989, and 7 supplements NUREG 1352, " Action Plans for Motor-Operated Valves and Check Valves," June 1990 Generic l.etter 96-05, September 18,1996.

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I STRUCTURE ACTION PLAN  !

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{ TAC No. M94164 Last Update: 1/7/96 i Lead NR.R Division: DE I Supporting Divisions: DRCH/DRPM j MILESTONES DATE (T/C) i 1. Develop action plan 09/96 (C) 5

2. Interface with NEl i

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a. NEl develop general industry gedance dc :vment for 7/96 (C) monitoring the condition of structures and 6ubmit the draft I

Guidance Document (NEl 96-03) to staff l b. Review and comment on NEl draft document (NEl 96-03, 10/96 (C)

Rev D) I i c. Submit final document to staff 2/97 (T) l i d. Complete staff review and issue staff evaluation report 3/97 (T)

(ECGB) i

e. Endorse NEl 96-03 through a revision of Regulatory Guide 5/97 (T) l 1.160 (for the Maintenance Rule only, see Milestone 3.b)

f. Endorse NEl 96-03 through a new Regulatory Guide (for the 8/97 (T)

[ License Renewal Rule, see Milestone 4.a)

3. Maintenance Rule Guidance (HOMB) l l a. NElincorporate staff comments on Rev D to NEl 96-03 2/97 (T) j adequately so that NEl 96-03 can be used as guidance for

, monitoring structures under the maintenance rule: OR NEl revise NUMARC $3-01 (Maintenance Rule Guidance) to

! include additional guidance for monitoring structures so that NUMARC 93-01 is a stand alone document. 5/97 (T)

.i b. If NEl guidance (to either NEl 96-03 or NUMARC 93 01) is 1 i acceptable, endorse through revised Regulatory Guide 1.160 TBD

< c. If necessary, revise IP 62706 (baseline inspections) and IP

! 62707 (monthly core maintenance inspection.)

4. License Renewal Guidance (PDLR)

a. Endorse NEl 96 03 for License Renewal through a new 8/97 (T)

Regulatory Guide. (The endorsement could be collectively or separately by maintenance and license renewal.)

b.* Prepare inspection procedure for inspection of structures as 8/97 (T) related to the license renewal rule (see Milestone 5.c) f 7

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5. Issues Associated with Operating Plants (ECGB)

{ a. Issue inspection Procedure 62002, "Inspectic,n of Structures, Passive Components, and Civil Engineering Features at Nuclear Power Plants" as related to the j maintenance rule.

1 (1). Develop draft IP 62002 7/96 (C)

{ (2). Issue draft IP for regional comment 10/96 (C)

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(3). Resolution of regional comments 12/96 (C)

(4). Issue final inspection procedure 12/96 (C)

b. Issue inspection procedure for inspection of containments in accordance with 10 CFR 50.55a which reference ASME i Section XI, Subsections lWE and lWL.

1 (1). Develop draft IP 3/97 (T)

$. (2), lasue draft IP for regional comment 5/97 (T) l (3). Resolution of regional comments 8/97 (T)

(4). Issue final inspection procedure 12/97 (T)

, c.* lasue inspection procedure for inspection of structures a3

related to the license renewal rule.

(1). Develop draft IP 8/97 (T)

(2). Issue draft IP for regional comment 9/97 (T)

(3). Resolution of regional comments 12/97 (T)

(4). Issue final inspection procedure 2/98 (T) 1,

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• Note: The lead technical branch will be established later.

Descriotion: This action plan was developed to identify and resolve major issues and problems in i monitoring the condition of structures at nuclear power plants as these issues and problems related j to ths maintenance rule, the license renewal rule, and plant operations, i Historical Backaround: On July 10,1991, the NRC published the maintenance rule (10 CFR e 50.65), which became effective July 10,1996. before regulatory implementation of the maintenance rule, the NRC staff conducted pilot site visits from September 1994 through March i 1995 to review early implementation of the maintenance rule. Through these visits, the staff

determined that most licensees had not established adequate monitoring of structures under the j mainter.ance rule and considered it a low priority. Some licensees incorrectly assumed that structures were inherently reliable and did not require monitoring or preventive maintenance. The i lessons learned from the pilot site visits were documented in NUREG-1626, " Lessons Learned from

Early implementation of The Maintenance Rule at Nine Nuclear Power Plants."

Separately and concurrently, the staff of the Civil Engineering and Geosciences Branch (ECGB) of j the Office of Nuclear Reactor Regulation (NRR) developed and published NUREG 1522, j " Assessment of Inservice Conditions of Safety-Related Nuclear Plant Structures," in June 1995, based on information obtained from six plant visits and numerous reported incidents. The ECGB staff concluded that safety-related structures need to be periodically inspected and maintained to ensure that they can adequately perform their intended safety functions.

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in 1991, at the same time the maintenance rule was issued, NRC also promulgated the license

renewal rule (10 CFR Part 54). This rule delineates the requirements for extending a license.

Although the two rules are similar in scope, and aspects of the maintenance rule may satisfy some requirements of the license renewal rule, the requirements of the license renewal rule go above and beyond the requirements of the maintenance rule. For example, the license renewal rule requires  ;

that licensees identify relevant aging effects and demonstrate that they will be adequately managed I to maintain the current licensing basis throughout the extended life of the plant. On March 4,

) 1996, NRC received Revision 0 to NEl 95-10, " Industry Guideline for implementing the 4

Requirements of 10 CFR Part 54 - the License Renewal Rule." However, NEl 95-10 did not specifically address the issue of monitoring the condition of structures.

! The NRC staff conveyed these findings regarding the inadequate monitoring of the condition of 1 l structures to the nuclear industry through NUREGs, public workshops, and interaction with NEl. I NEl has since issued draft versions of NEl 96-03, " Guideline for Monitoring the Condition of

Structures at Nuclear Power Plants." NEl intends to provide guidance to the industry by using this

document in conjunction with NUMARC 93-01, " industry Guideline for Monitoring the Effectivsness 4

of Maintenance at Nuclear Power Plants," for complying with the maintenance rule, and in

conjunction with NEl 9510 for complying with the license renewal rule.

Prooosed Actions: Actions included in the plan are to (1) review and interact with NEl on the issue of monitoring the condition of structures to comply with both the maintenance rule and the license renewal rule, (2) revise and issue regulatory guides to endorse NEl developed guidance documents, if they are found acceptable, and (3) issue inspection procedures for structures at operating plants.

1 Oriainatine Documents: NUREG-1526 and NUREG 1522.

l Reaulatorv Assessment: Completion of the activities in this action plan will result in guidance documentation that will provide a uniform and consistent method by which the industry and the j staff can monitor the condition of structures and ensure that unacceptable degradation is not occurring. For license renewals issued under Part 54, this activity is intended to develop guidance to ensure that structural margins are not compromised due to age related effects including the 4 consideration of changes in the dynamic response characteristics of structures and component

supports. These actions will provide guidance but impose no new requirements on licensees. At present, the NRC staff is monitoring the safety related maintenance issues on a case by case basis.

i There is no immediate safety issue. Accordingly, nonurgent regulatory action and continued facility operation are justified.

l . Current Stutig: NEl has formed a task force to develop a general industry guidance document on monitoring the condition of structures at nuclear power plants. NEl 96-03, " Guideline for

Monitoring the Condition of Structures at Nuclear Power Plants," Revision C, was sent to NRC for review on May 16,1996. NEl intends to use NEl 96-03 to meet the regulatory requirements for monitoring the condition of structures for both the maintenance rule and the license renewal rule.

The staff met with NEl representatives to discuss and provide comments on NEl 96-03 on June 17,

. 1996. NEl subsequently revised NEl 96-03 in response to the staff's comments and submitted Revision D for NRC's review on July 16,1996. The staff hes completed the review and sent its comments to NEl on October 1,1996.

NRR Technical Contacts

H. Ashar, ECGB, 415-2851 Thomas Bergman, HOMB, 415-1021 I

H. Wang, PDLR, 415-2958 NRR Lead PM: P. Wen, PGEB, 415-2832 l

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UPDATE OF SRP CHAPTER 7 TO INCORPORATE DIGITAL INSTRUMENTATION AND CONTROLS (l&C) GUIDANCE TAC Nos. M86367, M86392, M86423, Last Update: 12/27/96 i M86769, M86997, and M87680 Lead NRR Division: DRCH I GSI: Not Available MILESTONES DATE (T/C)

1. Develop Update of SRP Chapter 7 06/97T

2. ACRS Subcommittee Briefings 3/96C, 5/96C, 10/96C

3. Incorporate new Regulatory Guides (provided by 8/96C RES) in SRP Chapter 7 Update

4. Incorporate results from National Academy of 02/S7T Sciences study

5. Draft SRP to Chairman 9/19/96C

6. Publish Draft SRP Chapter 7 for Public Comment 03/97T

7. Incorporate Public Comments 3/97T

8. Final ACRS/CRGR Review of SRP Chapter 7 4/97T l

9. Final SRP to Chairman 3/31/97T

10. Publish Final SRP Chapter 7 5/97T Descriotion: This task action plan is used to track and manage the final phase of codifying the digital l&C regulatory approach and criteria by updating the existing Standard Review Plan (SRP) l Chapter 7. I Historical Backaround: By a staff requirements memorandum (SRM) dated November 30,1995, from the Chairman, Shirley Ann Jackson, to the Executive Director of Operations, James M. Taylor, the Chairman requested that the staff develop an action plan in the area of digital instrumentation and controls. The action plan is for the expeditious development of a Standard Review Plan (SRP) to ensure that safety margins are addressed and that NRC regulatory requirements are available and ready for use when reviewing licensee proposed installation of digital instrumentation and control systems in nuclear power plants. The staff has an ongoing effort for updating Chapter 7 of the SRP that deals with instrumentation and control systems to accomplish the requested action and this task action plan was initiated to track and manage the final phase of that effort in response to the SRM.

Pronosed Actions: Specific actions included in this task action plan are: (1) to develop the update of SRP Chapter 7, (2) to periodically brief the ACRS as sections of the SRP update are completed, (3) to incorporate new regulatory guides on digital l&C that will be provided by the Office of Nuclear Regulator) Research (RES), (4) to incorporate results from the National Academy of i Sciences (NAS) study of digital I&C at nuclear planc:, (5) to publish the draft SRP Chapter 7 for  !

public comments, (6) to incorporate the public comments, (7) to have final ACRS and CRGR review j of the SRP Chapter 7 update, and (8) to publish the fina: revised SRP Chapter 7.  !

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Oriainatina Document: The memorandum from the EDO to Chairman Jackson dated January 3,

) 1996, " Improvements Associated with Managing the Utilization of Probabilistic Risk assessment 4

(PRA) and Digital instrumentation and Control Technology."

Reaulatory Assessment: The approach and criteria that form the current regulatory framework for

review and acceptance of digital I&C systems in nuclear power plants is being codified in the 1

update to SRP Chapter 7. This framework has been communicated to the industry and public in

, safety evaluations for digital modifications to operating plants and design certification of the advanced teactor designs, and in Generic Letter 95-02, "Use of NUMARC/EPRI Report TR-102348,

' Guideline on Licensing Digital Upgrades / in Determining the Acceptability of Performing Analog-to-

,! Digital Replacements Under 10 CFR S0.59 dated" dated April 26,1995. This action plan tracks and manages the codification of the existing framework by updating SRP Chapter 7.

l Consequently, this is not an urgent regulatory action, and continued plant operation is justified.

Current Status: The staff and its contractor, Lawrence Uvermore National Laboratories (LLNL), are

currently revising the seven axisting sections of SRP Chapter 7 and developing two new sections and several new branch technical positions (BTPs) to incorporate criteria and guidance related to

digital l&C systems. In parallel, the Office of Nuclear Regulatory Research (RES) has developed l several regulatory guides that endorse national standards related to digital l&C.

j By the letter dated June 6,1996, the ACRS stated their agreement with the staff approach to the update of SRP Chapter 7, and their plan to continue to interact with the staff on the remaining changes to SRP Chapter 7. By memorandum dated September 16,1996, NRR requested CRGR

, review of the complete drrift SRP Chapter 7. In the minutes of CRGR Meeting Number 292 dated October 17,1996, CRGR endorsed the draft document for issuance for public comments. The complete SRP Chapter 7 update was presented to the ACRS in October 1996. By the letter dated

! October 23,1996, the ACRS stated that it had no objection to the staff's proposal for issuing the

draft SRP Chapter 7 for public comment. The updated draft SRP Chapter 7 was issued for i public comment and the notice of availability was published in the Federal Register on December 3, 1996. It was also posted on the NRC Homepage on the World Wide Web in December 1996.

Contacts: Matthew Chiramal, DRCH, 415-2845

! Joe Joyce, DRCH, 415-2842 i

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(

PRA IMPLEMENTATION ACTION PLAN 1.2(d)

Graded Quality Assurance Action Plan d

TAC Nos. M91429, M91431, M92420, Last Update: 1/2/97 l

, M92450, M92451, M92447, M92448, Lead NRR Division: DRCH M92449, M88650, M91431, M91432, Support Division: DSSA M91433, M91434, M91435, M91436, M91437 GSl: Not Available MILESTONES DATE (T/C) e

1. Issued SECY 95-059 03/95C

2. Begin interactions with volunteer licensees 05/95C

- Palo Verde letter dated 4/6/95 i - Grand Gulf meeting 5/4/95

, - South Texas meetings on 4/19/95 and 5/8/95 l

3. NRC Steering Group meetings to guide working level staff activities As Needed

- Meetings on: 8/25/95,10/10/95, 10/25/95

4. Staff interactions with Palo Verde Ongoing

- Site visit on 5/23/95 on ranking and QA controls through

- NRC letter dated 7/24/95 on proposed QA controls 1 - Site visit on 8/29-30/95 on risk ranking 6/97 i

- Site visit on 9/6-7/95 on procurement GA controls

- NRC letter conveying trip reports issued on 12/4/95

- Meeting on 4/11/96 to discuss the staff evaluation guide

- Letter from licensee on 4/24/96 providing comments on staff evaluation guidance Site visit on 6/5-6/96 to observe expert panel and review revised procurement QA controls, trip report sent to licensee on 8/6/96

- Letter from licensee on 9/12/96 transmitting responses to procurement issues raised in earlier staff trip reports

-letter from licensee dated 11/13/96 responding to PRA issms raised in 12/4/35 trip report 12

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S. Staff interactions with South Texas Ongoing

- Meeting on 7/17/95 on project status through l l - Site meeting on 10/3-4/95 on risk ranking and QA controls i

- Meeting on 12/7 8/95 to discuss risk ranking and QA controls 6/97

- South Texas Subrnittal of OA Plan for implementation of graded QA,

, dated 3/28/96 is currently under staff review

- Meetings on 4/11/96 and 4/25/96 to discuss the staff evaluation l

guide and future interaction milestones and schedules

- Letter from licensee on 4/17/96 providing comments on staff

evaluation guidance

- Meeting on 6/19/96 to discuss staff comments on the QA plan j submittal for graded QA, soview questions transmitted to STP on 8/16/96 l

- Site visit on August 21-22 to observe working group and expert i panel meetings, and to discuss staff review items, trip report in preparation

-Idanagement meeting on 10/15/96 to discuss PRA initiatives and i staff activities

- Letter from licensee dated 10/30/96 responding to PRA questions

- SECY paper to be prepared prior to staff approval of QA program change only if policy positions are taken in the staff approval l 6. Staff interactions with Grand Gulf Ongoing

- Site meeting on 7/11-14/95 to observe expert panoi through

- Meeting at hdqt. on 10/24/95 on QA controls 6/97

- Meeting at RIV on 11/16/95 on graded QA effort

- Site meeting on 11/17/95 to observe expert panel

- GGNS system and component ranking criteria under staff evaluation, the comments are scheduled to be provided to GGNS by

! the end of June Meeting on 4/11/96 to discuss the staff evaluation guide

- Letter to GGNS dated 5/29/96 regarding implementation of QAP commitments

- Staff review comments on GGNS safety significance determination process transmitted to licensee on July 15

- Meeting on August 27 to discuss staff comments on safety significance process and to discusa GGNS implementation of OAP commitments for low safety significant items, meeting summary issued on 12/17/96

- Site visit on 11/21/96 to review procurement activities, trip report in preparation

7. Revision 3 of Draft Evaluation Guide for Volunteer Plants issued for staff 07/95C comment

8. Revision 4 of Draft Evaluation Guide for Volunteer Plants issued for 10/95C Steering Group Review

9. Issue letter to 3 volunteer plants outlining program objectives and revbw j expectations. Distribute staff evaluation guide to licensees. 1/96C l I

13

{ 10. Evoluation Guide issued for use by staff in evaluating volunteer plants 1/96C

- Meeting held with volunteer plants to receive feedback on staff I

evaluation guide on 4/11/96. 4/96C

- Industry comments on staff evaluation guide provided by letter dated 5/24/96

- The staff will review the industry comments with respect to the need to revise, and finalize, the evaluation guide by the end of October.

- Meeting of GOA steering group will be scheduled to discuss i finalization of staff evaluation guide for volunteer implementation j phase I

, 11. Regulatory Guide and SRP development milestones per PRA Action Plan j

- Draft SRP and RG for Branch / division review and comment 7/31/96C

- Draft RG for inter-office review and concurrence 8/1/96C

- Draft RG for ACRS/CRGR review 11/22/96C

- Draft RG for public comment 3/31/97T

- Draft RG public comment period ends 6/3/97T j - Final draft RG for ACRS/CRGR review 9/1/97T i - Final draft RG for inter-office concurrence ~ 2/1/97T

- Publish final RG 12/31/97T l 12. ACRS Briefings

- Expert Panel and deterministic considerations 2/27 28/96C 1 - graded QA 4/11/96C

} - PRA Implementation Plan and pilot projects 7/18/96C j - Risk Informed Pilots 8/7/96C

- Graded QA Regulatory Guide 11/22/96C I 13. CRGR Briefings

! - Graded QA Regulatoy Guide 11/26/96C l 14. Issue Lessons Learned NUREG report regarding Graded QA Programs at 9/97T i volunteer plants 1

15. Public Workshop on Graded QA 2/98T f

j 16. Issue Staff Inspection Guidance (Reactive IP) 12/97T J

17. Conduct NRC Staff Training 1/98T

}

j 18. Issue SECY Update (close-out of action plan) 4/98T

}

l Descriotion: Prepare staff evaluation guidance and regulatory guidance for industry implementation for the grading of quality assurance (QA) practices commensurate with the safety significance of the plant equipment. The development of this guidance will be based on staff reviews of regulatory requirements, proposed changes to existing practices, staff development of a draft regulatory guide with input from a national laboratory, and assessment of the actual programs developed by the three volunteer utilities implementing graded quality assurance programs.

tiistorical Backaround: The NRC's regulations (10 CFR Part 50, Appendices A & B) require QA programs that are commensurate (or consistent) with the importance to safety of the functions to be performed.

However, the QA implementation practices that have evolved have often not been graded. In the development of implementation guidance for the maintenance rule, a methodology to determine the risk significance of plant equipment was proposed by the industry (NUMARC 93-01). During a public meeting on December 16,1993 the staff suggested that the industry could build on the experience gained from 14

-- __ . - . . . . - - - .. . -- .- . . - - - - ~ - . -

i

. the maintenance rule to develop implementation methodologies for graded QA. The staff had numerous interactions with the Nuclear Energy institute (NEI) during calendar year 1994 as the graded QA concepts

were discussed and the initial industry guidelines were developed and commented on. In early 1995, j three licensees (Grand Gulf, South Texas, and Palo Verde) volunteered to work with the staff. The staff has reviewed the licensee developmental graded QA efforts.

Prooosed Actions: The goal of the action plan is to utilize the lessons learned from the 3 volunteer licensees to modify staff developed draft guidance to formulate regulatory guidance on acceptable methods for implementing graded QA. The staff will develop a regulatory guide based in part on input 4

from Brookhaven National Laboratory, and a reactive inspection procedure (IP) for graded QA. An inter-

office team has been established to prepare the regulatory guidance documents and test their

, implementation during the evaluation of volunteer plant activities.

Oriainatino Document: Letter from J. Sniezek, NRC to J. Colvin (NUMARC) dated January 6,1994, describing the establishment of NRC stesting group for the graded QA initiative.

. Reaulatorv Assessment: Existing regulations provide the necessary flexibility for the development and 1

implementation of graded quality assurance programs. The staff willissue a NUREG report regarding the lessons learned from the volunteer plant implementations. Additional regulatory guidance will be issued to j either disseminate staff guidance or endorse an industry approach. Planned guidance for the staff will

involve an evaluation guide for application to the volunteer plants, the lessons learned report, training

sessions and public workshops, , and inspection guidance in the form of a reactive IP. The staff is evaluating the appropriate mechanism for inspections of the risk significance determination aspects of graded QA programs.

! The safety benefits to be gained from a graded QA program could be significant since both NRC reviews

! and inspections and the industry's quality controls resources would be focused on the more safety 1 significant plant equipment and activities. Secondarily, cost savings to the industry could be realized by l avoiding the dilution of resourcos expended on less safety significant issues. The time frame to complete this action plan is directly reisted to the overall PRA implementation plan schedules, j Current Status: A draft evaluation guide for NRC staff use has been prepared for application to the

volunteer plants implementing graded quality assurance programs. The staff will utilize the guide for the

review of the volunteer plant graded QA programs. The guide and the staff's proposed interaction i framework has been transmitted in a letter to the three volunteer licensees. The letter sought licensee comments. Outlines of a draft regulatory guide and SRP for both risk ranking and grading of QA controls have been prepared and circulated for review for the inter office team. A meeting was held with the three volunteer licensees on April 11,1996 to receive their feedback on the staff developed evaluation i guide. The licensees expressed concerns about the level of detail contained in the guide, particularly that l related to PRA and commercial grade item dedication. The licensees contend that exiting industry

guidance (PSA Application Guide and EPRI 5652) are sufficient for those topics. The staff received j written comments from NEl on the evaluation guide by letter dated May 24,1996. The NEl letter

) questions the need for additional regulatory guidance for the graded OA application. NEl contends that j existing industry guidance is sufficient. STP and PVNGS letters providing comments on the evaluation j guide were dated April 17,1996 and April 24,1996 respectively. The staff will compile suggested changes to the evaluation guide in response to the industry comments and a meeting will be held to brief

~

. the graded QA steering group on the proposed changes, in addition, a presentation on graded QA was j made to the full ACRS on April 11th. During the ACRS meeting some questions arose with respect to the staff expectations for the conduct of expert panel activities.

! South Texas submitted their QA program revision for their graded QA effort on March 28,1996. The

] change has been reviewed by the staff (HOMB, SPSB, RES, RIV, and NRC contractors). A meeting was

! held with STP on June 19 to discuss the staff's comments and concerns. STP indicated their willingnsss i to re-examine the content of the QA plan with respect to the proposed QA controls for the low safety 1

1 15

i significant items. The staff visited the site on August 21-22 to receive information from STP in response to earlier staff questions about the STP approach towards determining safety significance categorization and adjustment of QA controls. The staff also observed both a Working Group and Export Panel meeting

, at which time licensee safety significance evaluations fcr 2 systems (Radiation Monitoring and Essential i Service Water) were discussed. Staff review will resume when STP submits a revision to the OA program to address staff concerns.

i Also, NEl submitted 96-02, " Guideline for implementing a Graded Approach to Quality" dated March 21,

! 1996. The staff has performed a cursory review of the document and concluded that it does not reflect

the progress and level of detail that has been achieved through the volunteer plant effort. The staff informed NEl by letter dated May 2,1996 that the guide la not adequate (as a stand alone document) to

implement graded QA but that it will be considered as the staff develops the graded QA regulatory guide and standard review plan. By letter dated June 8, NEl indicated that their 96-02 guide will be revised.

Further NEl requested a meeting with the staff (in the August time frame) to discuss the changes and to

discuss more objective means to assess the adequacy of OA program implementation. NEl has proposed l '

that the seied 96-02 guidelines will be submitted to the staff for endorsement by a regulatory guide. l A subsequent letter was received from NEl on July 16 that provided an updated version of NEl 96-02

based on comments they received from the volunteer plants and industry sources. The staff will review the modified document and then brief the steering group on the results. On October 10,1996 NEl l submitted a letter expressing their concern with the graded OA initiative. NEl stated their concerns regarded the questions raised by the staff in the area of OA controls for items determined to be low safety significant and in the area of safety significance determination. A meeting with NEl has been scheduled on January 23,1997 to discuss their concerns.

NRR

Contact:

S. Black 415-1017, R. Gramm 415 1010

! RES

Contact:

R. Woods 415-6622 2

Refereossa:

) 1) Letter from J. Sniezek (NRC) to J. Colvin (NEI) dated 1/6/94 1 J 2) Regulatory Guide 1.160

3) NUMARC 93-01, " Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear i Power Plants"

! 4) SECY 95-059, " Development of Graded Quality Assurance Methodology",3/10/95 l 5) Letter from B. Holian (NRC) to W. Stewart (APSCo) dated 7/24/95 3 6) Letter from C. Thomas (NRC) to W. Stewart (APSCol dated 12/4/95

7) Memorandum from S. Black to W. Beckner and W. Bateman dated 1/24/96, Draft Staff Evaluation i Guidance

8) NEl 96-02, " Guideline for Implementing a Graded Approach to Quality" 5

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l NEW SOURCE TERM FOR OPERATING REACTORS TAC No. M89586 Last Update: 1/3/97 GSI No.155.1 Lead NRR Division: DRPM Supporting Division: DSSA & DE MILESTONES DATE (T/C) 1

1. NEl Letter 7/94C I

2. Commission Memo 9/94C

3. NEl Response 9/94C l

4. NEl/NRC Meeting 10/94C

5. Publication of NUREG-1465 2/95C

6. NEl/NRC Meetings 10/94C, 6/95C,10/95C,1/96C, 2/96C, 5/96C, 8/96C

7. Submittal of Generic Framework Document (from NEI) 11/95C

8. First Pilot Plant Submittal 12/95C l l

9. Issue Memo to Commission, Updating Status 8/06C

10. Present Commission Paper in E-Team Briefing 9/96C l

11. Brief CRGR on Commission Paper 10/96C l

12. Send Commission Paper to EDO/ Commission 11/96C

13. Brief ACR3 on Commission Paper 11/96C

14. Response to NEl Framework Document 1/97T

15. Begin Pilot Plant Reviews 1/97T

16. Begin Rebaselining 1/97T

17. Finish Rebaselining TBD

18. Finish Pilot Plant Reviews TBD Descriotion: More than a decade of research has led to an enhanced understanding of the timing, magnitude and chemical form of fission product releases following nuclear accidents. The results of this work has been summarized in NUREG-1465 and in a number of related research reports. Application of this new knowledge to operating reactors could result in cost savings without sacrificing real safety margin. In addition, safety enhancements may also be achieved.

His'orical Backaround in 1962, the U. S. Atomic Energy Commission published TID-14844, " Calculation of Distance Factors for Power and Test Reactors." Since then licensees and the NRC have used the accident source term presented in TID-14844 in the evaluation of the dote consequences of design basis accidents (DBA).

After examining years of additional research and operating reactor experience, NRC published NUREG-1465, " Accident Source Terms for Light-Water Nuclear Power Plants," in February 1995. The NUREG describes the accident source term as a series of five release phases. The first three phases (coolant, 17

1 3

jI i gap, and early in-vessell are app'icable to DBA evaluations, and all five phases are applicable to severe accident evaluations. The DBA source term from the NUREG is comparable to the TfD source term; J I

' however, it includes a more realistic description of release timing and composition. Since the NUREG source term results in lower calculated DBA dose consequences, NRC decided not to require current plants to revise their DBA analyses using the new source term. However, many licensees want to use the

, new source term to perform DBA dose evaluations in support of plant, technical specification, and procedure modifications.

NRC and NEl met several times to discuss the industry's plans to use the new source term. To make efficient use of NRC's review resourcos, NRC encouraged the industry to approach the issue on a generic ,

basis. The Nuclear Energy Institute (NEI) unveiled its plans for the use of the new source term at I i operating plants at the Regulatory information Conference in May 1995. NEl, Polestar (EPRI's I i consultant), and pilot plant (Grand Gulf, Beaver Valley, Browns Ferry, Perry, and Indian Point) l representatives met with NRC staff in June and October 1995 to discuss more detailed plans. i Pronosed Actions: The staff has reviewed the framework document has prepared a Commission paper l and decision letter that describes a generic implementation approach. The staff presented the j Commission paper and decision letter to the NRR Executive Team in September, briefed CRGR in October, j and briefed tho ACRS full committee in November. The staff sent the Commission paper and decision letter to the Commission in November 1996 (SECY 96-242). As described in the Commission paper, the

} current plan is to rebaseline 2 NUREG-1150 plants; one a PWR and one a BWR. The staff will also review

! each pilot plant application and prepare an exemption package addressing the use of each feature of the i j NUREG 1465 source term while pursuing rulemaking. The plan for issuing each remaining generic

exemption is to brief the CRGR, issue for public comment, and then issue the exemption.

Oriainatina Document: EFRl Technical Report TR-105909, " Generic Framework Document for Application j of Revised Accident Source Term to Operating Plants," transmitted by letter dated November 15,1995.

l 4

Reaulatorv Assessment: There will be no mandatory backfit of the new source term for operating l reactors. The design basis accident analyses for current reactors based on the TID-14844 source term are still valid. Therefore, non-urgent regulatory action and continued facility operation are justified.

l 1

i Current Status: NEl submitted its generic framework document in November 1995 for NRC review and i approval. TVA submitted part$f its pilot plant application for Browns Ferry in December 1995. The staff

! met with NEl on January 23,1996 to discuss the generic framework document and separate meetings

! were held on February 7, May 3C and August 29,1996 to discuss the Browns Ferry, Perry, and Grand

! Gulf pilot plant submittals, respectively. Indian Point, and Oyster Creek are also expected to submit pilot plant applications. The staff met again with NEl and the industry on October 2,1996 to discuss the staff's plan to issue exemptions while pursuing rulemaking. The staff has completed its review of the framework document and prepared a Commissicn paper describing how it intends to conduct its generic i rcview of pilot plant submittals.

The staff briefed the NRR Executive Team on SECY 96-242 in September, the CRGR in October, and the ACRS full committee in November. A limited number of pilot plants submittals and exemptions are expected - three submittals have been received so far (Browns Ferry, Perry and Indian Point-2).

! Applications are also expected from Grand Gulf and Oyster Creek. In addition, the staff and Virginia l Power met on November 26,1996 to discuss the rebaselining of Surry.

1 l NRR Technical Contacts: R. Emch, PERB, 415-1068 A. Huffert, PERB, 415-1081 NRR Lead PM: J. H. Wilson, PGEB, 415-1108

References:

N'UREG-1465, " Accident Source Term for Light Watre Nuclear Power Plants," February, j 1995.

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July 27,1994, letter to A, Marion, NEl, from D. Crutchfield, NRC, " Application of New Source Term to

. Operating Reactors".

I September 6,1994, letter to the Commission from NRC staff, "Use of NUREG-1465 Source Term at

, Operating Reactors".

4 j July 21,1995, letter to the Commission from NRC staff, "Use of NUREG-1465 Source Term at Operating Reac t.y s".

] December 22,1995, pilot plant submittal. letter to Document Control Desk from Tennessee Valley Authority, " Brown's Ferry Nuclear Plant (BFN) - Units 1, 2, and 3 - Technical Specifications (TS) No. 356 2

and Cost Beneficial Licensing Action (CBLA) 08 - Increase in Allowable Main Steam Isolation Valve (MSIV) q Lea! age Rate and Request for Exemption from 10 CFR 50, Appendix J... and 10 CFR 100, Appendix l A...".

r August 9,1996, memorandum to the Commission from NRC staff, "Use nf NUREG-1465 Source Term at

Operating Reactors".

Summaries of public meetings:

e dated November 10,1994 for public meeting with NEl held on October 6,1994; j

• dated July 26,1995 for public meeting with NEl held on June 1,1995;

• dated November 17,1995 for public meeting with NEl held on October 12,1995.

j e dated February 1,1996 for public meeting with NEl held on January 23,1996.

j e dated February 27,1996 for public meeting with Browns Ferry held on February 7,1996

e dated September 27,1996 for public meeting with Grand Gulf held on August 29,1996 l e dated October 11,1996 for public meeting with NEl on October 2,1996 1

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ENDANGERED SPECIES ACTION PLAN l

TAC No. M88282 Last Update: 1/3/97 l GSI: El-184 Lead NRR Division: DRPM MILESTONE DATE l

1. Development of action plan. 06/95C

2. Develop list of currently listed protected species in the vicinity of each 11/95C nuclear power plant site

3. Identify individuallicensee programs and activities being conducted to 05/96C further the conservation of protected species.

4. Determine priority for sites warranting follow-up actions. 01/97T I

5. Recommend site-specific follow-up actions to Projects. 02/97T

6. Development and implementation of process for maintaining status and 04/97T compliance with the ESA at each site.

I Descriotion: Develop a list of currently listed protected species in the vicinity of each nuclear power plant l site, identify individuallicensee programs and activities being conducted to further the conservation of l protected species, and conduct informal or formal consultation with either the National Marine Fisheries Service or the Fish and Wildlife Service, as warranted fer any specific site, i Historical Backaround: In 1973, Congress passed the Endangered Species Act for the protection of l endangered or threatened species. In responding to a Commission memorandum of July 30,1991, concoming efforts of the Commission, applicants, and licensees for protection of endangered species in the vicinity of nuclear power facilities, it was identified that the NRC may not have completed all the necessary activities required by the Endangered Species Act for some of the facilities that have identified endangered species. This action plan will determine the additional actions, if any, that need to be taken at individual sites so that the NRC can meet its obligations under the act. l Pronosed Actions: Conduct evaluations of plant-specific lists of endangered species and existing licensee l commitments to further the conservation of the protected species and determine if informal or formal I consultation with either the National Marine Fisheries Service or the Fish and Wildlife Service is warranted.

Oriainatino Dngument- Commission Memorandum of July 30,1991.

Raoulatorv Assessment: Continued facility operation is appropriate because this action plan does not involve a health and safety issue.

Current Status: A list of currently listed protected species in the vicinity of each nuclear power plant site was developed by a contractor and delivered to NRC on 4/25/96. This report is now under review. This action plan will be evaluated with respect to separating generic and plant-specific aspects as part of Milestone 4. The contractor will provide a final report in October that prioritizes sites and makes recommendations for followrup actions.

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_ .. ~ . ..= . . _ _ . _ . _ - - - -. . - -.-~ -.-

l Contacta:

NRR Tochttical Contacts: Mike Masnik, PDND, 415-1191 Jim Wilson, PGEB, 415 1108 NRR Lead PM: Jim Wilson, PGEB, 415-1108

References:

Commission Memorandum of July 30,1991.

I Note: The Endangered Species Act requires Federal agencies to take appropriate actions to ensure l protection of endangered or threatened species.

I 21

I ENVIRONMENTAL SRP REVISION ACTION PLAN l TAC No. M80177 Last Update: 01/07/97 l GSI: Not Available Lead NRR Division: DRPM l '

l l

MILESTONES DATE (T/C) 1

1. Reflect Potential Impacts and Integrated impacts in Options for Resolution

a. Identification of potentialimpacts 03/96C

b. Identification of integrated impacts 06/96C

c. Proposed options for resolution and develop initial draft 10/96C of revised ESRP

d. Staff / contractor meeting to resolve format and content )

of revised ESRP 11/96C l 2. Prepare Final Draft of ESRP Sections for Public Comment

a. Draft updated ESRP for staff review 02/97T

b. ACRS and/or CRGR review, if necessary 06/97T

c. Publish (electronic) for public comment 08/97T

3. Disposition Public Comments 01/98T

4. Publish Final NUREG-1555 08/98T

5. Maintenance of program data Ongoing Brief Descriotion: The Environmental Standard Review Plan (ESRP) Revision Action Plan deals with the revision to NUREG-0555 to reflect changes in the statutory and regulatory arena, to incorporate emerging environmental protection issues (e.g., SAMDA and environmental justice) since originally published in  !

1979, and to support the review of license renewal applications. The ESRP will take the form of the SRP l (including acceptance criteria) and follows the same update criteria outlined under the SRP-UDP project (with the exception of maintaining the MDB at this time). The objective of the tasks outlined in the action plan is to complete the identification of potential impacts by April 1996 (completed in March 1996), the integrated impacts by June 1996 (completed), and the options for resolution beginning in August 1996 with levelizing across-ologies occurring earlier at the options stage rather than later at the draft stage.

Initialinteractions on options stage indicate that, at a minimum, the existing ESRP sections will need restructuring to conform to NUREG-0300 format; contractor is combining resolution options and format restructuring to accelerate schedule. After submittal of the draft by February 1997 for staff and CRGR review, if necessary, the sectire . will be published for public comment in August 1997. Disposition of public comments and staff review of the update (NUREG-1555) leads to a publication date of August 1998.

Reaulatory Assessment: NRR has established the ESRP Update Program for use in the life cycle review of environmental protection issues for nuclear power plants, especially license renewal applications, but also operating reactors, and future reactor site approval applications. The ESRP will reflect current NRC requirements and guidance, consider other statutory and regulatory requirements (e.g., the National Environmental Policy Act, Presidential Executive Orders), and incorporate the generic environmental impact work and plant-specific requirements developed during amending of Part 51 for license renewal l

reviews.

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l Current Status: The PNNL/NRC staff workshop on the restructured and revised ESRP was held during '

November 13-14, 1996. Now that the Part 51 rule for license renewal is final, particular emphasis is being placed on assuring that license renewal needs are being adressed in a schedule consistant with the RES regulatory guide and pilot plant application.

I 4 NRR Technical

Contact:

B. Zalcman, PGEB, 415-3467 4

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]! 10 CFR 50.59 ACTION PLAN I.

j TAC No. M94269 Last Update: 12/31/96 4

i Lead NRR Division: DRPM i Supporting Divisions: all '

a i

MILESTONES DATE (T/C) l j 1. Action plan approval / copy to Commission (04/15/96)(C)

! 2. Identify work group members 05/24/96(C) ,

j  !

3. Brief D/NRR on issues N/A a

i 4. Conduct workshop 06/18/96(C) l 5. Brief D/NRR on proposed positions 07/24/96(C) j 6. Draft position papers 08/29/96(C) a

7. Obtain regional comments 09/30/96(C) 1 -

l 8. Policy issues and position paper to Commission with (01/24/97)(T) s Lessons Learned Report

-f

9. Issue document for public comments (2/97)(T)

10. Obtain comments, including ACRS 04/97(T) l 11. Revised positions and recommendations issued to NRC (08/97)(T) management

12. Commission Paper (08/97)(T) l 13. Follow-up Actions TBD 1

I Descnotion: This action plan defines measures to improve licensee implementation and NRC staff oversight of the 10 CFR 50.59 process, f Historical Backaround: 10 CFR 50.59 was promulgated in 1962 to describe the circumstances under

)

i which licensees may make changes to their facility (or to make changes to procedures, or to conduct  ;

i~

tests and experiments) without prior NRC approval when the change does not involve the Technical '

Specifications or an unreviewed safety question. Licensees are required to submit periodically information related to changes made pursuant to 50.59. The NRC has programs for monitoring licensee processes for implementing 50.59. In a memorandum dated October 27,1995, Chairman Jackson raised a number of questions concerning 50.59 implementation and NRC oversight, and proposed a systematic reconsideration and reevaluation of the process.

1

! The December 15,1995, memorandum from the EDO responded to the specific questions and stated that 4

within 120 days from the date of the memorandum, the staff would review previously issued guidance on 4

implementation of the 50.59 process to define areas where the guidance needs to be amended and to develop an action plan to identify actions to be undertaken to improve both the licensee's implementation and the NRC staff's oversight of the 50.59. The staff has completed its review of existing guidance and

! has identified certain issues for further examination, which this action plan addresses. The staff has

made the results of its review of guidance, the action plan, and its interim inspection guidance publicly available.

i 24

Pronosed Actions

The staff's approach to development of regulatory guidance would proceed in phases.

j Over the next several months, the staff will attempt to provide npocific positions (guidance) to accomplish

! the objectives listed below, and will evaluate the feasibility of implementing such guidance within the existing regulatory framework. At the end of the first phase, estimated to take about eight months, the staff would take stock of its progress and make recommendations on issuing guidance, undertaking j

rulemaking or other actions.

1

! Specifically, the objectives of this effort are to develop guidance that wuuld:

J

! o define the elements of safety evaluation review or screening processes within the context of i various licensee design or change control processes, to provide greater assurance that effects on

safety of changes, whether to equipment, procedures, or methods of system operation, are )

appropriately evaluated.

I

o define more specifically the scope of applicability of 50.59 (that is, to identify those changes, tests, or experiments) that need to be evaluated to determine if NRC approvalis needed). This

would include a more comprehensive description of change, and guidance for broader j consideration of "as described."

i o establish the process for resolving nonconforming conditions such that differences from the FSAR I l are reconciled (from both safety and regulatory viewpoints) in a time frame commensurate with l their safety significance. This will also consider when such conditions should be evaluated under j 50.59 as temporary modifications because resolution of the nonconforming condition has been delayed.

P l o improve USO determinations in the following respects:

address the extent to which short and long term compensating actions may be considered 2

as part of change under 50.59 so that it can be determined that the probability has not i increased or margins of safety as defined in the basis for any technical specification has l not been reduced. Also address when consideration of compensating actions should be l reviewed as part of the basis for approving a proposed license amendment.

t -

clarify the extent to which PRA techniques may be usefulin evaluating the effects on I

safety of a change, and in addressing the " probability may be increased" criterion for

} unreviewed safety questions.

clarify what is meant by " margin of safety" in relation to numerical parameters, analysis methods, calculated results of safety analyses, and licensing limits such that changes that might affect the basis for staff's safety conclusions with respect to Technical i Specifications are more consistently identified.

j Finally, as part of the development of possible guidance, consider whether additional definitions are needed, such as for malfunction of equipment important to safety.

J Public comments on the position paper (s) will be obtained. The ACRS will be requested to provide its comments on these positions. Actions, milestones and schedules for further phases of this nffort will be developed after the results of the first phase are assessed.

3 4 in the area of staff oversight, the staff conducted, on June 18,1996, a roundtable discussion with I regional staff, resident inspectors and NRR staff who have participated in 50.59 inspection efforts to

! share experiences and to discuss such topics as the mix of programmatic and implementation reviews, sampling and team composition. Appropriate changes to inspection procedures will be made, i

)

1 25

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1 Other related efforts are being tracked under other programs.

1 Oriainatina Document: April 15,1996 memorandum from the EDO to Chairman Jackson,

Subject:

Action Plan for Improvements to 10 CFR 50.59 Implementation and Oversight.

3 i

Reaulatory Assessrnant: The action plan was developed to identify actions to improve

{ implementation of the 50.59 process. A number of improvements have been implemented in the last few

months, such as directing inspectors conducting all routine inspections to specifically address FSAR j compliance, and reviewing spent fuel pool / core offload proce' lures and practices at al! facilities. As i stated in the December 15,1995, memorandum, "The staff concludes that there is currently no indication l that implementation of 10 CFR 50.59, as it is carried out today, has led to decreased safety, based on i inspection experience. While improvements can be made to achieve a highw degree of uniformity of I

review, the current process as it is being implemented provides reasonable assurance that plant safety i has not been decreased." The above conclusion is confirmed by the additional analysis of inspection i

experience presented in the staff review document. Therefore, non-urgent regulatory action and continued facility operation are justified.

Current Status

A revision to the action plan was issued on August 20,1996, which revised the i scheduled milestones such that the Commission will have the opportunity to consider the policy issues i associated with 50.59 along with other policy issues from the Millstone lessons learned review, i

The present schedcle is for submittal of the draft position paper to the Commission on

! January 24,1997, which is also the date for forwarding the Part 2 Millstone Lessons-Learned Report.

The position paper, and the Commission paper were distributed for internal comment on December 20,

! 1996, with comments requested by January 7,1997. Comments are under evaluation.

NRR Technical

Contact:

E. McKenna, PGEB, 415 2189 l

References:

October 27,1995 memorandum from Chairman Jackson to EDO f

1 j November 30,1995 memorandum from Chairman Jackson to EDO 4

j December 15,1995 memorandum from EDO to Chairman Jackson j December 28,1995 memorandum from EDO to Chairman Jackson t

April 15,1996 memorandum from EDO to Chairman Jackson August 20,1996 memorandum from EDO to Commission 26

l INDUSTRY DEREGULATION AND UTILITY RESTRUCTURING ACTION PLAN

! 1 l TAC Nos. M78003 Last Update: 12/31/96  !

GSI: Not Available Lead NRR Division: DRFM l MILESTONES DATE (T/P/C)

I Task 1 - Develop NRC Policy Statement and SRP 05/97T '

Draft Policy Statement 05/96C Office Concurrences 06/96C EDO Concurrence 06/96C l Commission Paper 07/96C l' Draft SRP 07/96C l Publish Draft Policy Statement 09/96C l Office Concurrences on SRP 09/96C EDO Concurrence on SRP 09/96C l

Commission Paper on SRP 09/96C Publish Draft SRP 12/96T l PubHc Comment Policy Sta'.ement 09/96C Public Comment SRP 02/97T Final SRP/ Policy Statement 03/97T Office Concurrences 03/97T ACRS 03/97T CRGR 03/97T EDO Concurrence 04/97T Commission Approval 05/97T Publish Final SRP and Policy Statement 05/97T Task 2 - Issue Administrative Letter to Licensees on Financial Reporting 06/96C Requirements Draft Administrative Letter 05/96C Office Concurrences 05/96C Commission Information Paper 06/96C lssue Admin Ltr to Licensees w/WTR Letter to CEOs 06/96C Task 3 - Develop Non-Rulemaking Option for Periodic Reporting 2/97T Requirements as Necessary Determine Necessity for Action 09/96C Draft Option 01/97T Office Concurrence 01/97T CRGR Review 01/97T EDO Concurrence 02/97T i Publish Draft 02/97T i

I i

27 l

l

4 Task 4 - Update prior NUREG documents on owners and antitrust license 02/97T conditions issue Task Order Contract 05/96C Draft NUREG Updated 09/96C f

Publish NUREGs 12/96C Public Comment 01/97T Revise and Publish Final 02/97T Task 5 - Institutionalize Staff Level Contact with NARUC,SEC,FERC. ONGOING Develop MOUs as necessary.

, Letter to agencies 06/96C Staff level meetings 11/96C Draft MOUs to Commission (as required) TBD Sign MOUs TBD Task 6 - Develop and implement rulemaking to clarify 10 CFR 50.80 if TBD necessary Commission determination of need TBD Proposed ANPR or rulemaking package TBD Office Concurrences TBD ACRS Comments TBD CRGR Concurrence TBD l EDO Concurrence TBD l Commission Approval TBD Publish ANPR or Proposed rule TBD Public Comment TBD Revise Rulemaking Package TBD Office Concurrences TBD ACRS Comments TBD CRGR Concurrence TBD EDO Concurrence TBD Commission Approval TBD Publish Final Rule TBD Task 7 - Assist Office of Research (RES) on Decommissioning Funding ONGOING Assurance Rule.

Milestones for this task provided by RES under rulemaking action,

" Decommissioning Costs and Funding Evaluations" Descriotion: The action plan is intended to address the Commission's concerns regarding the irnpact of utility deregulation and resulting reorganizations and restructuring on licensee's financial qualifications and their ultimate ability to safely operate and decommission their facilities.

28

. . . . - - . . . - . - . - . - - - . - _- ~_ - - .- ~ - . . - - . - . - - . - ..

1 i

1 1

Historical Backaroundi in recent years, several restructurings and reorganizations have occurred with the i electric utility industry, in addition, State public utility commissions (PUCs) have increased pressure for j improvements in economic performance of electric utilities they regulate in order to reduce the rates paid

by wholesale and retail consumers. The accelerated pace of this restructuring may affect the ability of

power reactor licensees to pay for safe plant operations and decommissioning. Specifically, the l restructuring may affect the factual underpinnings of the NRC's previous conclusion that power reactor l licensees can reliably accumulate adequate funds for operations and decommissioning over the operating )

' lives of their facilities.

J 4 i

Pronosed Actions: Specific actions included in the action plan are: (1) issuing a policy statement I l delineating NRC's expectations with respect to future financial and anti trust reviews and developing a {

standard review plan regarding NRC's current financial review requirements; 2) issuing an administrative i

! letter to alllicensees delineating their current responsibilities with respect to getting prior NRC approval

! for changes that may affect their previous financial qualification determinations or ownership; 3)

! formulating non-rulemaking periodic reporting requirements, j 4) updating NUREG documents containing financial information: 5) establishing staff level contacts with the Securities and Exchange Commission (SEC), the Federal Energy Regulatory Commission (FERC), and the National Association of Viity Regulatory Commissions (NARUC); 6) implementing rulemaking if

, necessary; and 7) assisting the Office of RES in their decommissioning funding assurance rulemaking.

Current Status; PGEB has developed a draft policy statement, administrative letter, and liaison letters to

)

FERC and SEC. Staff level contacts with NARUC have been identified. The administrative letter was i j issued with a letter to the CEOs of all licensees on June 21. A Commission Information Paper informed

, the Commission of our intentions for sending the Admin letter and CEO letter. A Commission Paper I j forwarding the draft policy statement was submitted on July 2,1996, as SECY-96-148. The l

, Commission approved publication of the draft policy statement by SRM dated August 16,1996. The )

l draft policy statement was published in the Federal Register on September 23,1996. PGEB and OGC l j staff met with FERC counterparts on October 10,1996. A meeting with SEC representatives was held i i on November 7,1996.

l 4 4

NRR Technical Contacts: R. Wood, PGEB, 415-1255 j I M. Davis, PGEB, 415-1016 i

I 4

i 29 l l

l

EXTENDED POWER UPRATE ACTION PLAN TAC No. M91571 Last Update: 01/08/97

Lead NRR Division: DRPW

GSI: RI-182 Supporting Division: DSSA MILESTONES DATE (T/C) 1: Receive GE Topical ELTR1 (Generic Review Methodology). 3/95 C 2: Issue Staff Position Paper on ELTRI Meeting with GE/NSP. 4/95 C

- Identify differences between LTR1 and ELTRI. 8/95 C Issuo RAls as appropriate. 9/95 C l

- incorporate information on foreign experience obtained from 10/95 C i SRX8.

Develop power uprate database for all U.S. plants. 10/95 C

- Issue Staff Pncition Paper. 2/96 C i 3: Receive GE Topical ELTR2 (Generic Bounding . Analyses).

l GE plans to submit ELTR2 in two parts: the first part in March 96 3/96 C and the second oart in July 1996. .7/96 C l 4: Issue Staff SE on GE ELTR2.

Meeting with GE/ industry. 2/96 C l -

Issue RAls as appropriate. 2/97 T

- Input to the SE from technical branches. 6/97 T Issue SE. 7/97 T l 1

l j 5: Receive Lead Plant Application (Monticello). 7/96 C  ;

3 1 6: Issue Staff SE for Lead Plant.

l l -

Meeting with Monticello. 10/96 C j -

RAls input from tech branches. 1/97 C

]

Issue RAls as appropriate. 2/97 T Input to the SE from tech branches. 8/97 T ACRS Presentation 9/97 T 1 - Issue Secy information Paper 10/97 T Issue SE. 10/97 T i

j 7: Develop a Standard Review Procedure. Incorporate lessons laarned 12/97 T

. from Lead Plant activity.

2 l Descriotion: This action plan describes the strategy for completing both the generic and plant-specific reviews for extended power uprate submittals for boiling water reactors (BWRs). General Electric Company (GE) submitted a licensing topical report (ELTR1), which outlines the methodology for implementation of an extended power uprate program. ELTR1 encompasses power uprates of up to 120 percent of the originallicensed thermal power. Individual plant submittals for uprates wi!!likely contain requests for an optimum power level specifb for that plant which is something less than the full 120 percent.

30

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I l i

j The technical branches will review the applicable portions of the ELTR2, GE topical report containing i

generic analyses and the lead plant application, and provide input into both safety evaluation reports. '

Review criteria from the reviews performed on ELTR1, generic analyses, and the lead plant submittal will be developed and assembled into a review procedure for individual PMs to use for subsequent plant-

[ specific reviews. If an area in an individual rjant submittal is outside the bounds of the previously a

established criteria, the applicable technical branch will perform a review of that specific area and provide input into the safety evaluation.

I Historical Backaround: The generic BWR power uprate program was created to provide a consistent means for individual licensees to recover addtional generating capacity beyond their current licensed limit.

in 1990, GE submitted licensing topical reports to initiate this program by proposing to increase the rated l thermal power levels of the BWR/4, BWR/5, and BWR/6 product lines by approximately 5 percent. Since 1990, the staff has reviewed and approved at least 9 such power uprate requests under this generic BWR i power uprate program. As a follow-on to this program, GE submitted ELTR1 in March 1995 to propose j " extended" power uprates of up to 120 percent of the originallicensed thermal power.

l Pronossd Actions: Specific actions included in the generic action plan are: (1) review ELTR1 and issue a 1

staff position paper, (2) review ELTR2 and !ssue a safety evaluation report, (3) review the lead plant application and issue a safety evaluation report, and (4) develop a standard review procedure based on

! ELTR1, ELTR2, and the lead plant review. .

i )

, Oriainatino Document: GE Licensing Topical Report (NEDC-32424), " Generic Guidelines for General i Electric Boiling Water Reactor Extended Power Uprate," dated February 1995.

4 l Reaulatorv Assessment: Not applicable. (A safety assessment is not needed for this action plan because

a justification for cor'tinued operation of a plant is not required.) This program is an industry initiative that is strictly voluntary, i I

l Cygg,nt Status:

The overall schedule for staff review of both the lead plant submittal and the GE submittal has been j revised to incorporate the " lessons learned" from the Maine Yankee experience as well as the Brunswick

. exporience.

i l NRR Lead PM: T. J. Kim, DRPW, 415-1392 i

i 1

l l I

a k .

a  ;

l  !

, \

i 31

l DRY CASK STORAGE ACTION PLAN TAC Nos. M93821 (issue 2.a) Last Update: 01/09/97 M93927 (issue 3.b) Lead NRR Division: DRPW

, M94107 (issue 4.c.)

M94108 GSI: Not Available i

MILESTONES DATE  !

. (T/C)

1. Develop action plan 07/95C 1

2. Near-term technical issues

a. Heavy Loads / Cranes j

- develop working group plan 11/95C

- complete actions 6/97T l b. Cask Trunnions' f - develop staff position 09/95C modify standards / guidance No changes required (C) i c. Hydrostatic Testing 12/95C

d. Seismic Requirements for Pads 06/95C

- issue Information Notice

3. Long term technical issues

e. Cask weeping'

- meet with NEl 08/95C

, - determine NRC actions to resolve As Necessary l j 1,. Cask loading / unloading procedures l

- contact NEl about industry efforts 08/95C

. - resolve high priority issues 09/95C

- form working group 10/95C i - complete working group determination on further issues 04/96C

c. Off Loading after fuel pool is decommissioned'

- develop guidance and modifications to inspection As required in procedures response to submittals

d. Failed Fuel Storage'

- review proposed solutions Reviewing first '

submittal, ECD 03/97T

e. Safeguards Concerns'

- complete analysis of designs 12/95C 2

NMSS has the lead for this issue.

32

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~

MILESTONES DATE (T/C)

4. Procedural issues

a. Change processes

- issue SRP and 50.59 guidance 03/96C training for staff 05/96C

b. Reporting Requirements'

- develop position, communicate to licensees 09/95C

c. Inspection of site activities

- issue revised procedures 02/96C

- develop resource estimates and inspection schedule 02/96C

d. Vendor inspections'

- issue revised procedures 02/96C

- develop resource estimates and inspection schedule 10/95C

e. Cask and SAR differences'

- contact vendors 09/95C

5. Communications

a. Interface meetings Oncoing

b. Staff training' 10/95C

c. Industry workshop

• 07/95C Descriotion: The Plan was developed to identify and resolve major issues and problems in the area of dry cask storage of spent reactor fuel in independent spent fuel storage installations (ISFSis)f Specific issues encompassed by the plan include heavy load control, procedures for cask loading and unloading, failed fuel storage, change processes, insg action activities, and communications (internal and external). Issues have been divided into the following categories: near-term technical, long-term technical, communications, and process issues.

Historical Backaround: Since 1986, several U.S. nuclear power plant licensees have installed independent spent fuel storage installations (ISFSis), that is, licensee-owned dry cask storage facilities. Other licensees are also planning such installations. In recent years, licensees have encountered a number of problems during the fabrication, installation and licensing of some of these ISFSis and there has been an inconsistent level of performance by involved licensees and cask fabricators with respect to the use of dry cask storage of spent reactor fuel. Because of the anticipated increased industry effort in this area, the staff needed to fully understand the problems that occurred and take appropriate measures to reduce such problems in the future. Therefore, NMSS and NRR reviewed the lessons learned from past experience with ISFSis, both our experience and the experience of other headquarters and regional offices, and developed a plan to resolve major issues and problems.

Pronosed Aqtigaa: Actions included in the plan are: (1) review each general issue and identify the 4

specific problems to be addressed, (2) develop corrective actions for each problem, and (3) implement the corrective actions.

Oriainatina Document: Memorandum from Carl J. Paperiello and William T. Russell to James M. Taylor, July 28,1995, " Dry Cask Storage Action Plan".

8 An additional workshop has been tentatively scheduled for May 1996.

33

l l

j Reaulatory Assessment: The plan addresses dry storage of fuel that is several years old. Technical j issues have been addressed on a site-specific basis for existing facilities. The action plan willimprove guedance, enhance communications with industry and the public, and aid future applicants.

l

} fagent Status: The following action plan issues have been completed: cask trunnions, cask weeping, j hydrostatic testing, safeguards concerns, Part 72 reporting requirements, inspection of site activities, and vendor inspections. The inspection procedures for dry cask activities (site and vendor) were issued in i

February,1996. These procedures included resource estimates for inspection actbities. The staff has i incorporated additional guidance on seismic issues into inspection Procedure (IP) 60851 and additional guidance concerning consideration of failed fuel in unloading procedures into IP 60854. The working

! group has completed its review of the issues associated with cask loading and unloading. The working j group is implementing its recommendations, including the preparation of an information notice concerning loading and unloading issues. Recent information (e.g., hydrogen ignition at Point Beach) may require

.C*ns to the action plan. The schedule for the remaining technical issue (heavy load control) has been A

extendea !o allow resolution of issues related to NRC Bulletin 96-02, issued April 11,1996. In addition, issues related to Oyster Creek licensing actions and 50.59 evaluations may provide insights into the final resolution of the control of heavy loads. The issue of potential cask drop events prior to securing the lids will be resolved as part of closure of Bulletin 96-02. The variety of issues related to heavy loads and impact on staff resources may justify a separate action plan. The staff are reviewing and resolving public comments received on the draft dry cask storage SRP. Lessons learned from the hydrogen ignition event at Point Beach are being incorporated into the SRP as well as inspection procedures. All of the communications issues are ongoing efforts with no specific criteria for closure. However, there have been significant improvements in these areas. The Regions, NMSS, and NRR hold regular interface calls to discuss dry cask issues, training has been given to the affected staff, and NRC has established open  ;

communications with the newly-formed Nuclear Energy Institee Dry Cask Storage issue Task Force. I Based on these improvements, the staff will review these issues for closure in the next major update of l the action plan. The ECD for the review of the first submittal for the storage of damaged fuel has been I changed to 03/97 due to untimely responses from the applicant. NMSS/SFPO sponsored a public i workshop on dry cask storage on May 17,1996. Well over 300 people attended from the plants, states, j industry groups, vendors, and the staff. The staff briefed the Commission on the status of the dry cask l storage program on May 30,1996. In response to a hydrogen ignition event at Point Beach on May 28, the staff issued information Notice 96 34 on May 31,1996 NRC Bulletin 96-04 on July 5,1996. The  !

bulletin requires all storage and transportation cask vendors and users to submit a report to the NRC that documents evaluations of cask material compatibility with all environments that the casks are expected to ,

encounter. Staff review of the bulle*in responses is ongoing. A major update to this action plan, for l issuance by 2/97, is being coordinud between NRR and NMSS/SFPO. Negotiations are continuing as to whether this action plan should be closed (based on tasks being completed and/or included in other action plans and normal NMSS/SFPO case work) or continued in existing form pending final resolution of all open items (with potential addition of several recent items currently tracked separately by NRR and NMSS).

NRR

Contact:

William Reckley, DRPW, 415-1314 NMSS

Contact:

Patricia Eng, SFPO, 415 8577 References Memorandum from Robert M. Bernero and Willam T. Russell to James M. Taylor, March 15, 1995, " Realignment of Reactor Decommissioning Program" Memorandum from Carl J. Paperiello and William T. Russell to James M. Taylor, July 28,1995, " Dry Cask Storage Action Plan" Memorandum from Carl J. Paperiello and William T. Russell to James M. Taylor, January 25,1996,

" Update to the Dry Cask Storage Action Plan" 34

ACCIDENT MANAGEMENT IMPLEMENTATION TAC #: M91966 - Overall Last Update:12/20/96 M91641 - BWROG SAMG Review Lead NRR Division: DSSA MILESTONES DATE (T/C) .

1. Review BWROG Severe Accident Management 04/97T Guidance (SAMG) documents

2. Review severe accident training materials and 06/95C BWROG prioritization methodologies

3. Develop Tl for pilot inspections initial draft (for internal use) 11/95C Site visits of "in-progress" activities TBD Revised draft (to NEl and public) TBD Final Tl TBD ,

4. Complete pilot inspections and follow-up 12/97T

5. Revise inspection procedures (IP) and hold public workshop Draft IP 03/98T '

Public meeting / workshop 05/98T Final IP 07/98T

6. Review remaining plants TBD  !

Descrintion: This action plan is intended to guide staff efforts to assess the quality of utility imp!ementation of accident management (A/M), and the manner in which insights from the IPE program have been incorporated into the licensees A/M program. Specific review areas willinclude: development and implementation of plant-specific severe accident management guidelines (SAMG), integration of SAMG with emergency operating procedures and emergency plans, and incorporation of severe accident information into training programs.

. Historical Backaround: The icsue of A/M and the potential reduction in risk which could result from

• developing procedures and training operators to manage accidents beyond the design basis was first identified in 1985 [1]. A/M was evaluated as Generic issue 116 and subsumed by A/M-related research activities in late 1989. Completion of A/M is a major remaining element of the Integration Plan for Closure of Severe Accident issues [2]. The development of generic and plant-specific risk insights to  ;

support staff inspections utility A/M programs is also identified in the Implementation Plan for Probabilistic Risk Assessment [31. NRC's goals and objectives regarding A/M were established at the inception of this program (41. Generic A/M strategies were issued in 1990 for utility consideration in the !PE process 15].

The staff has continued to work with industry to define the scope and content of utility A/M programs and these efforts have culminated in industry-developed A/M guidance for utility implementation.

Industry has committed to implement an accident management program at each NPP [61. NRC has accepted the industry commitment and developed tentative plans for staff inspection of utility implementation [7].

Pronosed Actions: Specific actions included in the A/M action plan are: (1) complete the review of BWROG SAMG documents, (2) conduct site visits in early 1997 to observe how the elements of the formal industry position are being implemented, (3) complete the draft Temporary instruction (TI) using the information and perspectives obtained through the site visits, (4) complete pilot 35

l t

l k

j inspections and follow-up, and (5) develop an inspection procedure for use at remaining plants and hold a j public workshop. Based on feedback from the workshop, the staff will finalize the inspection procedure,

[ and the approach and schedule for evaluating A/M implementation for the remaining plants.

4 l Oriainatina Document: SECY 88-147, Integration Plan for Closure of Severe Accident issues, May 25, 1988.

i

(

Raoulatorv Assessment: Accident management programs are being implemented by licensees as part of I an initiative tu further reduce severe accident risk below its current, and acceptable, level. Consecuently, I l this is a non-urgent regulatory action and continued facility operation is justified. i

! Current Status: Severe accident management guideline documents have be abmitted by each of the

PWR owners groups, and reviewed by the staff. The BWROG submitted a a were accident management I overview document on February 3,1995, and a response to staff comments on the overview document

! on March 6,1996. The BWROG submitted Rev, O of the Emergency Procedure and Severe Accident l Guidelines (EP/ SAG) and associated technical basis documents to NRC for information on August 29,

1996. The staff has contracted with Oak Ridge National Laboratory to perform a high level review of the EPG/ SAG documents. A draft TER was received in early December and is currently under staff review, i

The BWROG has agreed to illustrate the EP/ SAG implementation process and time-line by applying the l' guidelines to a limited number of BWR sequences. The NRC has provided the BWROG information on accident sequences of interest for this purpose, and is anticipating a submittal from the BWROG in

January 1997. A meeting to discuss specific questions / concerns regarding the BWROG products is

expected in February 1997 .

)

i Licensee target dates for completing A/M imolementation have been submitted to NRC, and a draft Tl for l use in the pilot inspections has been completed. Comments on the draft Tl have been received from the i NRC Region offices. The staff met with industry on February 22,1996 and ACRS on March 1,1996 to

discuss plans for inspecting utility implementation of the formal industry position on severe accident j management and major elements of the draft TI. These plans include staff visits to approximately 2 to 4 ,

i sites for the purpose of obtaining an early understanding of how the various elements of the formal J industry position are being implemented. The information and perspectives obtained through these visits as well as comments from the regional offices will be used to update the draft Tl. The draft Tl will be made available to NEl and the public after the information-gathering visits.

The informction gathering visits have not yet occurred due to an inability of NEl to identify licensees that are either piepared or willing to support the visits at this time (NEl had agreed to coordinate this effort.)

A meeting with NEl to discuss the scope and schedules of the information gathering visits was held on December 19,1996. At that time, NEl proposed to take the lead in organ! ring " demonstrations" of completed A/M implementation at four to six plants. These demonstrations would be in lieu of the information gathering visits and follow-on pilot inspections envisioned by the staff, and would occur in the June / July 1997 timeframe. As proposed, industry (through NEI) would play a Dreater role in defining the scope, depth, and acceptance criteria for the demonstrations, and would deal collectively with NRC l concerns on any issues that arise during the demonstrations. A draft of the Industry SAMG l Demonstration Process was provided for staff consideration. A follow-up meeting with NEl to discuss staff views on the industry proposalis anticipated in late January 1997 l Technical Contacts:

NRR Technical

Contact:

R. Palla, SCSB, 4151095 NRR Lead PM: Ramin Assa, DRPW,415-1391 36

- .--_ _ , = _

l 1

4

References:

1. Memorandum from F. Rowsome to W. Minners, "A New Generic Safety lasue: Accident Management," April 16,1985

! 2. SECY 88-147, Integration Plan for Closure of Severe Accident issues ,

l

3. SECY-95-079, implementation Plan for Probabilistic Risk Assessment l I

. 4. SECY-89-012, Staff Plans for A/M Regulatory and Research Programs t

l 1

5. Generic Letter 88-20, Supplement 2, April 4,1990 i 1

6. Letter from W. Rasin to W. Russell, November 21,1994 l 2

j 7. Lstter from W. Russell to W. Rasin, January 9,1995 i

i 4

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i

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a 37

i FIRE PROTECTION TASK ACTION PLAN f'

. TAC Nos.M86652, M82809, M84592, Last Update: 12/15/96 M85142, and M89509 Lead NRR Division: DSSA

GSI: LI-181

' l MILESTONES DATE (T/C)

I 1. Sem! annual Commission status reports Last: 10/31/96C Next: 04/30/97T s

j 2. Recommendations for 01/97T l action (Part 1) 3.

Recommendations for 10/96C

future study (Part II)

4. Confirmation issues (Part lil) 10/96C l

5. Other issues (Part IV) 08/95C j

]

Descnotion The Fire Protection Task Action Plan (FP TAP) is used to track and manage implementation of the recommendations made in the " Report on the Reassessment of the NRC Fire Protection Program,"

i of February 27,1993.

! j 1 Historical Backaround: In February 1993, the Office of Nuclear Reactor Regulation (NRR) completed a reassessment of the reactor fire protection review and inspection programs in response to programmatic  !

concerns raised during the review of Thermo-Lag fire barriers. The results of the reassessment were documented in the " Report on the Reassessment of the NRC Fire Protection Program," of February 27,1993. The staff prepared the FP-TAP to implement the recomrnendations made as a result 1 of the reassessment report.

Prooosed Actions: The FP-TAP tracks the implementation of a wide range of technical and programmatic fire protection issues, it includes recommendations for action (Part I), recommendations for further study (Part II), confirmation issues (Part Ill), and lessons learned (Part IV). The staff is implementing the recommendations, in priority order, as resources allow. The staff focus is now on implementing its plan for future direction of the NRC fire protection program with emphasis on the fire protection functional inspection (FPFI) program and centralizing the management, by NRR, of the FPFI program and all other l reactor fire protection work. The principal objective of these efforts is to ensure that the NRC has a '

strong, broad-based and coherent fire protection program which is commensurate with the safety significance of the subject.

Qriainatino Document: " Report on the Reassessment of the NRC Fire Protection Program,"

February 27,1993.

l Raoulatorv Assessment: Each operating reactor has an NRC-approved fire protection plan that, if properly implemented and maintained, satisfies 10 CFR 50.48, " Fire protection," and General Design Criterion 3,

" Fire protection." Therefore, each plant has an adequate level of fire safety and the individual action plan items are receiving appropriate priority.

Current Status: The staff issued a semiannual report to the Commission on the status of the FP-TAP on October 31,1996. The next status report is due to the Commission on April 30,1997.

38 1

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l

\

l The staff completed additional small-scale fire tests of fire barrier materials other than Thermo-Lag at f4lST. The test results were provided by NIST in its Report of Test FR 4008, " Pilot-Scale Fire-Endurance Tests of Fire-Barrier Panels and Panet/ Blanket Combinations," dated August 20,1996. The staff's review l of the Report of Test FR 4008 is ongoing.

The Plant Systems Branch (SPLB) continued to work with Probabilistic Risk Assessment (PRA) Branch staff and Brookhaven National Laboratory (BNL), its technical assistance contractor, to evaluate the risk associated with the post fire safe shutdown methodology that imposes a self-induced station blackout. l The staff plans to apply the PRA model for assessing the risk significance of the self-induced station ,

blackout methodology to two plant-specific cases during FY 97. The staff is working on an issue l

recommended for further study regarding fire barrier reliability, under Generic Safety lasue (GSI).149,

" Adequacy of Fire Barriers." The staff and BNL have performed scoping analyses, using fault trees and event trees, to assess the effectiveness of a degraded fire barrier in mitigating the consequences of a fully developed fire in a plant area that is important to post fire safe shutdown. The staff and BNL discussed the preliminary results of these two studies and future plans with the Advisory Committee on Reactor Safeguards (ACRS) on February 29,1996. By letter of March 15,1996, the ACRS submitted its comments to the Commission. The staff responded to the ACRS by letter of April 25,1996. The staff is assessing the recommendations made by the ACRS and has referred these comments to the PRA Review Committee for further consideration.

In SECY 96-134, the staff stated that as part of the new fire protection rulemaking, it would review operating experience and would address a variety of fire safety issues. Consistent with this commitment, l and to eliminate duplication of effort, the staff has included its review of some of the FP-TAP issues in its plan for the fire protection rulemaking. These include, for example, a review of the adequacy of operability requirements for safe shutdown equipment and of fire barrier surveillance requirements, l

adequacy of manual firefighting, and the remaining confirmation issues. The staff will track these issues ~

in the fire protection rulemaking plan rather than in the FP TAP. This action, which completes Part 111 of the FP TAP, is documented in a memorandum of October 31,1996, from J. Taylor to the Commission.

Scientech and BNL are providing technical assistance for developing the Fire Protection Functional inspection (FPFI) procedures. BNL has completed its work. Scientech plans to complete its work during December 1996. The NRR staff is preparing a SECY paper to inform the Commission of the details of the FPFI program and to provide staff plans for implementing the program. The staff has selected 12 candidate pilot plants (3 per region). The staff is currently working with the regional offices to select 4 final candidates (1 per region) and to schedule the 4 FPFI pilot inspections. The staff plans to begin the pilot inspections with an initial draft procedure no later than the first quarter of calendar year 1997.

The development of a fire protection training program is on hold until the FPFI program is implemented.

Contact:

D. Oudinot, DSSA, 301 415-3731

References:

" Report on the Reassessment of the NRC Fire Protection Program," of February 27,1993.

SECY-95-034, " Status of Recommendations Resulting From the Reassessment of the NRC Fire Protection Program," February 13,1995.

Memorandum of October 31,1996, from J. M. Taylor, EDO, to the Commission, " Semiannual Report on the Status of the Thermo-Lag Action Plan and Fire Protection Task Action Plan."

39

i

{ PRA IMPLEMENTATION ACTION PLAN TAC Nos. M90370, M90371, M90227, Last Update: 12/19/96 l M90977, M91787-M91802 Lead NRR Division: DSSA 1 GSI: Not Available

]

MILESTONES DATE(T/C) j 1. ACRS Meeting 07/94C 2

08/96C 11/96C 12/96C

[ 03/97T j 2. Commission Briefing 08/94C l 04/95C 04/96C l 10/96C 04/97T

3. Publish PRA Policy Statement for 60-day comment period 12/94C 4, ACRS Subcommitteo Meetino 3 09/94C 4

' 07/96C 4

11/96C 01/97T 02/97T

5. Conduct Public Workshop on PRA Implementation Plan 12/94C

6. Publish final PRA policy statement 08/95C l

~

7. Detailed implementation NA

1.1(a) Develop draft Standard Review Plans for risk-informed 02/97T  :

regulation for ACRS review  ;

{ 1.1(b) Forward draft Standard Review Plans to the Commission 03/97T I 1.1(c) Final draft Standard Review plans for ACRS review 9/97T j j l 1.1(d) Publish final Standard Review Plans 12/97T 1.2 Pilot Applications to Specific Regulatory initiatives:

(a) MOVs (b) IST (a) 02/96C (c) ISI (b) 06/97T (d) Graded QA (c) 06/97T (e) Maintenance Rule (d) 06/97T (f) Technical Specifications (e) 09/95C (g) Other applications to be identified later (f) 03/97T 1.3(a) Develop inspection Guidance to Use IPEs and Plant-Specific 06/97T PRAs 1.3(b) Develop training course for inspectors 05/97T 1.3(c) Support regional inspection activities Ongoing 40

.-.- -- - . - - - - -- . ..-. .. - - .- - - .-~.- - - .- -..-.- -

)

i i

MILESTONES DATE{T/C) 1.4 Operator Licensing - Revise Examiner's Handbook to Reflect 03/97T j Revised Knowledge & Abilities Based on Risk Insights

1.5 Event Assessment -

i (a) Conduct event assessment of reactor events (a) Ongoing i (b) Assess desirability of risk assessment on non-power (b) TBD J

{ reactors d

] 1.6 Review Adequacy of Licensee Analysis in IPEs/IPEEEs 06/97T 1.7 Apply Guidance to Assess Effectiveness of SBO and ATWS 09/97T

! Ruks l

1.8(a) Staff review of PRAs for design certification applications Ongoing j 1.8(b) Develop SRP for Review of PRAs for Evolutionary Reactor 12/99T  ;

Designs '

1.8(c) Develop Guidance for Use of Risk in Simplification of 12/96T Emergency Planning Requirements

1.9 Accident Management - Develop Risk Insights to Review and TBD Inspect Industry Accident Management Programs f

i 1.10 Evaluate IPE insights to determine followup activities 12/97 s

l Descriotton: This action plan is intended to describe the process for the staff to use PRA method and j technology in the agency's effort toward risk-informed regulatory approach. The plan encompasses a

methods development, pilot applications, and staff training. The plan will be used to ensure timely and j

integrated agency-wide effort that is consistent with the PRA Policy Statement.  ;

i Historical Backaround: The NRC has been making use of PRA technology to varying degrees in its regulatory activities since WASH 1400. Prior to 1991, this had been an ad hoc application, depending on

{ the availability of expertise in various technical groups. Since 1991, there have been a number of high-

! level studies within NRC that have focused on the status of PRA use and its role in the regulatory

, process. Collectively, the findings and recommendations from these studies support the view that there l is a need for increased emphasis on PRA technology applications. For the full value of our investment in i risk assessment methodology to be achieved, it is important that consistent high-level agency guidance be l provided on the appropriate use of PRA. To this end, in November 1993, the Office Directors of NRR, 1 AEOD, NMSS, and RES proposed to take the initiative in providing guidance on coordination and

expectations for PRA efforts. Specifically, they proposed to develop an integrated plan for the staff's risk

! assessment and risk management practices. In August 1994, the staff submitted SECY 94-219,

] " Proposed Agency-Wide implementation Plan For Probabilistic Risk Assessment," for the Commission's j information. On March 30,1995, The staff submitted SECY-95-079, " Status Update of the Agency-Wide j implementation Plan for PRA," and briefed the Commission on the subject on April 5,1995. On May 18, i 1995, the staff forwarded SECY-95126, " Final Policy Statement on the Use of Probabilistic Risk Assessment Methods in Nuclear Regulatory Activities," for Commission vote. On June 8,1995, the staff briefed the ACRS on the PRA policy statement. The final PRA policy statement was published in the Federa/ Reg / ster on August 16,1995.

Pronosed Actions: The PRA Implementation Plan includes activities for NRR, RES, AEOD, and NMSS staff to increase the use of PRA methods in all regulatory matters. NRR focuses on the PRA applications in reactor regulations, the development of standard review plans, the pilot programs to use PRA technology in specific regulatory initiatives, events assessment, and working with regions on risk-informed 41

inspections. RES focuses on the IPE/IPEEE reviews, PRA method and quality, and the development of PRA regulatory guides for the industry. AEOD focuses on risk-informed trends and patterns analysis, reliability data for PRA applications, and staff training. NMSS focuses on using PRA in high and low level waste issues. The detailed actions are described in the PRA Implementation Plan.

Oriainatino Document: Memorandum dated November 2,1993, T. Murley et al. to J. Taylor, " Agency Directions For Current and Future Uses of Probabilistic Risk Assessment".

Reautatory Assessment: This action plan is meant to improve the regulatory process by developing state-of the-art PRA tools that will expand the use of PRA technologies in making regulatory decisions. The plan is not intended to correct safety problems at licensed facilities. Therefore, continued facility operation is justified.

Current Status: As discussed in the memorandum from the EDO to Chairman Jackson dated December 10,1996, the draft risk-informed RGs and SRPs that were scheduled to be completed in December 1996 are now scheduled to be completed by March 31,1997.

The risk-informed ISI RG and SRP are based on the Nuclear Energy Institute (NEI) guidelines and insights gathered from the methodology review of one pilot plant. Submittals from pilot plants have been substantially delayed. However, the staff had significant interactions with the industry and pilot plant applicants to allow the development of the draft RG and the draft SRP. The NEl has indicated that it is planning to meet with the staff in December,1996, or January,1997, to discuss an integrated approach that incorporates the ASME and the EPRI risk-informed ISI methodologies into a single guideline. The staff plans to review and, where appropriate, incorporate aspects of the NEl integrated guidelines into the draft RG and draft SRP by March 1997. The staff will meet with the ACRS and CRGR to discuss the revised documents and intends to forward the revised draft RG and SRP for risk-informed ISI to the Commission by May 31,1997. l The staff is evaluating the pilot licensees'submittals for risk-informed IST (Comanche Peak and Palo Verde); however, a shift in resources from work on the pilot applications to work on the RGs and SRPs has contributed to delays in these pilot projects. In the process of developing the RG and SRP for risk-i informed IST, the staff has identified a number of significant technical issues that remain to be resolved in l order for the staff and licensees to agree on a pilot approach to risk-informed IST. The staff is preparing requests for additionalinformation and making plans to discuss them with licensees. Accordingly, the staff has postponed submitting its recommendation to the Commission on implementing the risk-informed IST at the pilot facilities from March 1997 unti! June 1997.

The staff's recommendation to the Commission regarding the risk-informed TS pilot (Task 1.2) has been delayed 3 months from the earlier schedule because the staff decided to visit a third pilot site before ending its review of the SIT and LPSI changes and because its resources shifted from work on the pilot l applications to work on the RGs and SRPs. The staff now expects to send its recommendation on the TS pilot applications to the Commission by March 31,1997. Guidance for risk informed inspection procedures related to 50.59 evaluations and regular maintenance observations has been delayed until October 1997 to allow utilization of revised inspection manual guidance.

The Inspection Manual Chapter 9900 revision which provides technical guidance on the use of PRAs in the power reactor inspection program was issued to regional offices for review and comment in October ,

1996 (Task 1.3). Because significant risk informed inspection resources were diverted to maintenance l rule baseline inspections and because a number of significant comments were received from the regional  ;

offices, the schedule for developing PRA-related inspection guidance has been changed to June 1997.

l Also, due to this resource reallocation, guidance for risk-informed inspection procedures related to 50.59 evaluations and regular maintenance observations has been delayed until October 1997. This delay will 42

i allow the staff to ensure that these inspection activities are consistant with the high level risk informed guidance being developed in Manual Chapter 9900.

In the October 1996 PRA Implementation Plan update (SECY 96-218), the staff indicated that it could not conclude, from the licensees' submittals, that all the licensees met the intent of Generic Letter 88-20. In that Commission paper, the staff indicated that essentially all IPE reviews will be completed by December 1996, but that due to delays in responses from several !icensees to staff questions, approximately three IPE SERs will not be completed by December 1996. Because of additional delays in receiving licensee information and in reviewing additional licensee submittals, this number is now between five and eight.

In regard to the application of risk insights in operator licensing (Task 1.4), the staff recommended in SECY-96-123, " Proposed Changes to the NRC Operator Licensing Program," that the revised operator licensing process be implemented on a voluntary basis with the issuance of Revision 8 of NUREG-1021,

" Operator Licensing Examination Standards for Power Reactors," and that the Commission approve the staff's pursuit of rulemaking to require power reactor facility licensees to prepare the operator licensing examinations in accordance with NUREG-1021. In a staff requirements memorandum (SRM) dated July 23,1996, the Commission asked the staff to develop a detailed rulemaking plan to justify changes that may be necessary to 10 CFR Part 55 and directed the staff to address a number of issues regarding the proposed examination process. The staff responded to the SRM with SECY 96-206, "Rulemaking Plan for Amendments To 10 CFR Part 55 to Change Licensed Operator Examination Requirements," on September 25,1996, and is still awaiting a decision from the Commission. If the Commission approves the new examination methodology, the staff will publish Revision 8 of NUREG-1021, Revision 8 will be implemented six months after the date of publication. The staff expects a Commission decision before March 1997.

NRR Technical Contacts: Tom Hiltz, SPSB, 415-1105 1 i

References:

SECY-94-219, " Proposed Agency Wide implementation Plan for Probabilistic Risk Assessment" l SECY-95-079, " Status Update of The Agency-Wide implementation Plan for Probabilistic Risk Assessment" SECY 95126, " Final Policy Statement on The Use of Probabilistic Risk Assessment Methods In Nuclear Regulatory Activities" SECY-95-280, " Framework For Applying Probabilistic Risk Analysis in Reactor Regulation" Memorandum from James M Taylor to Chairman Jackson, " improvements Associated with Managing The i Utilization of Probabilistic Risk Assessment (PRA) and Digital Instrumentation and Control Technology,"

January 3,1996.

Memorandum from James M. Taylor to the Commission, " Status Update of the Agency-Wide implementation Plan for Probabilistic Risk Assessment (PRA) (From March 30,1995 to February 29, 1996)," March 26,1996.

Staff Requirements - Briefing on PRA Implementation Plan,10:00 a.m., Thursday, April 4,1996, Commissioners' Conference Room, One White Flint North, Rockville, Maryland (Open to Public j Attendance), May 15,1996.

Memorandum from James M. Taylor to the Commission, " Status Update of the Agency-Wide implementation Plan for Probabilistic Risk Assessment (PRA) (From March 1,1996 to May 31,1996),"

June 20,1996.

43

4 Letter from T. S. Cross, ACRS Chairman to Chairman Jackson, NRC, " Risk-informed, performance-based regulation and related matters" dated August 15,1996.

SECY-96-218, " Quarterly Status Update for the Probabilistic Risk Assessment (PRA) Plan, including a Discussion of Four Emerging Policy lasues Associated With Risk-informed Performance-based Regulation,"

. October 11,1996.

1 Memorandum from James M. Taylor to Chairman Jackson, " Status of the Development of Risk-Informed Regulatory Guides and Standard Review Plans," December 10,1996.

4 4

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i 3

i I

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4

4 4

! ENVIRONMENT AL QUALIFICATION TASK ACTION PLAN 1

TAC No. M85648 Last Update:12/16/96 GSI: 168 Lead NRR Division: DSSA 1

i MILESTONES DATE (T/C)

1. Inform Commission 05/93C j 2. Meet With Industry Ongoing 1 \

l 3. Programmatic Peview 1/97i i

4. Risk Assessment 1/97T

5. Data Collection and Analysis 4/96C ,

i  ;

j 6. Review and Evaluation of the Status 12/96T

7. Technical lasues 10/98T

8. Options for Resolution TBD

9. Implementation TBD Descnotion: This action plan will evaluate environmental qualification (EO) issues, including operating experience, testing methodology, and adequacy of current rule and 00idance for operating reactors. It will resolve EQ issues for aging onrating reactors and license renewal.

Historical Backorgy.0.d: A review of environmental qualification requirements for license renewal and failures of qualified cables during research tests led to the development of the EQ Task Action Plan (TAP),

which was issued in July 1993. The EQ TAP was developed to address: (1) staff concerns regarding the differences in EQ requirements for older and newer plants; (2) concems raised by some research tests which indicate that qualification of some electric cables may have been non-conservative; and (3) concerns that programmatic problems identified in the staff Fire Protection Reansessment Report might ,

also exist in the NRC EQ Program. I Prooosed Actions: The EQ TAP includes meetings with industry, a program review of EO, data collection and analysis, a risk assessment, and research on 80i ng and condition monitoring. Annual Commission papers are written to update the status of the EQ TAP. The staff will develop options for resolving EQ concerns, which may include issuing a generic letter, changing the rule, or documenting the acceptabuity I of the current EQ ru!a and standards. The basis for the appropriate regulatory action will be documented.

Oriainatino Document: June 28,1993, memorandum from Samuel J. Chitk to James M. Taylor (SECY 93-049); May 27,1993, letter to the Commission from J. Taylor on Environmental Qualification of Electric Equipment.

Raoulatorv Assessment: Depending on the appiication, failure of these cables during or following design-basis events could affect the performance of safety functions in nuclear power plants. There is no immediate safety issue because of the degree of conservatism already included in the EQ qualification test margins.

i 9

45 i

i

l

. l Current Status:

l The draft reports on the programmatic review and risk issues regarding EQ are currently under

management review (Milestones 3 and 4).

l BNL is continuing with the cable testing program, which includes investigating condition monitoring methodologies (Milestone 7). The first set of test cables are currently being preaged, and are expected to l j be LOCA tested at the end of January 1997. BNL reported that an agreement to purchase aged cables i from the Trojan nuclear power plant has been reached. BNL will acquire the aged cables for the cable tosting program in January 1997. Overall results from the test program are expected in fiscal years 1998  !

and 1999.

)

The staff issued an EQ-TAP update on November 15, 'i996, which included a discussion of its

! conclusions regarding the differences in requirements between older and newer plants.

i Contacts: NRR Technical

Contact:

G. Hubbard, SPLB, 415-2870

! RES

Contact:

S. Aggarwal, EMEB, 415-5849 l NRR Lead PM: L. Olshan, DRPE, 415-3018

References:

Letter to the Commission from J. Taylor on Environmental Qualification of Electric Equipment dated May 27,1993 (Accession No. 9308180153).

Staff requirements memorandum (SECY 93-049) dated June 28,1993

! (Accession No. 9409010107).

t l Task Action Plan for Environmentai walification and updates, Task Action Plan for Environmental

! Qualification and updates, July 1,1233, April 8,1994, November 16,1994, and June 27,1995

(Accession Nos. 9308120145, 9404260206, 950110431, 9507110203, respectively).

RES Program Plan for Environmental Qualification, July 7,1994 (Accession No. 9407250066).

4 i

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46 4

4 j CORE PERFORMANCE ACTION PLAN l TAC Nos. M91257 - DSSA Last Update: 12/19/96 M91602 - DISP Lead NRR Division: DSSA GSI: L1-179 Supporting Division: DISP MILESTONES DATE (T/P/C) j Task 1 - Inspection of Nuclear Fuel Vendors (DISP) 03/97T Siemens Power Corporation (PWR AIT folowup) 06/94C AB8/ Combustion Engineering (PWR reloads) 11/94C

Tesedyne-Wah Chang (TWC) 12/94C

Sandvik Specialty Metals (SSM) 12/94C Westinghouse CNFD 07/95C j General Electric NEP 10/95C I Framatome/Cogema Fuels (B&W Fuels) 09/96C 1 GE (SLMCPR & low density pellets)* 09/96C l ABB/CE [BWR) (WNP-2 transition core)* 06/97T SPC (comprehensive re-inspection of open items and new issues)* 04/97T Task 2 - Inspection of Licensee Reload Analyses (DSSA) ongoing

• RI - 3 ticensees (tbd): 12/97T Ril - 2 licensees (tbd); 12/97T Rlll - 3 licensees (tbd); 12/97T RIV - 2 licensees (tbd) 12/97T j Task 3 - Core Performance Data Gathering / Evaluation (DSSA) 12/97T Regions - Morning Reports & Event Notification ongoing

• Other - Data Acquisition and Collation ongoing PNL - Core Performance Evaluation Analysis (FY95) 12/96T Task 4 - Participation of Regions in Action Plan (DSSA) ongoing identification of Vendor issues Feedback from Licensee Inspections Counterparts Meetings (RI-RIV)

Task 5 - Evaluate Inspection Guidance (DSSA/ DISP) 5/97T Evaluate Results of Licensee inspections incorporate Feedback from Region Inspectors Draft Guidance for Resident and Region Inspectors issue inspection Criteria and Action Plan Update Task 6 - Evaluate Licensee / Vendor Lead Test Programs for Identification 12/97T*

of Core Performance Problems (DSSA/ DISP)

Task 7 - Workshop on Core Performance issues (TAC No. M95674)

Identify issues 07/96C Conduct workshop 10/96C Followup on Comments and Questions 03/96T

• leeue Driven 47

, - _ - - - - . _ - . - _ _ - . -- - - - - ~ - _- - -- . . _ - . - . ~

l l Descnotion: The action plan is intended to assess the impact of reload core design activities on plant

safety through inspections of fuel vendors, evaluation of licensee's reload analyses, independent l evaluation of core performance information, with regional training and interaction.

1 l

l Historical Backaround: The action plan addresses the review of feel fabrication, core design, and reload t

l analysis issues that were discussed during the March 29,1994, briefing given to James M. Taylor, ,

Executive Director for Operations. The briefing presented by the Reactor Systems Branch (SRXB), '

i Division of Systems Safety and Analysis (DSSA), covered generic fuel and core performance issues and j related evaluations of fuel failures. Representatives of the Vendor Inspection Branch (VlB), Division of j Reactor inspection and Licensee Performance (DRIL), participated in the briefing. As a result of this l briefing, the Office of Nuclear Reactor Regulation (NRR) was requested to prepare an action plan for a

{ proactive approach to monitor and improve core performance in operating reactors.

{

Pronosed Actions: Specific actions included in the action plan are: (1) evaluate fuel vendors'. .

performance through performance-based inspections that evaluate the reload core design, safety analysis, licensing process, fuel assembly mechanical design, and fuel fabrication activities; (2) evaluate the

performance of licensees that perform core reload analysis functions; (3) identify, document, and l categorize core performance problems and root cause evaluations that will be further evaluated during

these inspections and provide input to SALP evaluations as well as regional enforcement actions, as

! appropriate; (4) train and coordinate regional support staff participating in these activities; and (5)

! evaluate the results of these activities for use in formulating generic communications, revisions of

! regulatory guidance and guidance for regionalinspectors, and other appropsiate regulatory actions. In i addition, as a result of recent generic concems, including the failure of control rods to fully insert, the l action plan is being expanded to review the adequacy of vendor lead testing programs for new fuel

] designs (Task 6); and to conduct a workshop on core performance issues (Task 7) in the fall of 1996, as stated at the recent Regulatory Information Conference.

{

j DSSA - The action plan identifies that licensee inspections in each region shall be performed, in j i coordination with the regional inspectors, to assess licensee performance in reload core analysis oversight

! and participation. Licensee inspections will normally be issue-driven. The data acquired through licensee / vendor inspections will be integrated with information supplied by the regions and other sources j and will be evaluated for generic core performance indicators and industry conformance to current i regulatory requirements. The end product of the initial assessment will include guidance for resident

! inspectors and regional staff. These activities are scheduled to be completed in FY96. The ongoing l activities to capture and address early warning of emerging issues will continue into FY97, and the action j plan will be updated to reflect the planned inspection of 10 licensee / plants, 5 vendor LTA program inspections, and four anticipated event-reactive inspections.

DISP - The action plan currently identifies 8 completed and two planned vendor inspections that shall be performed by multi-disciplined inspection teams lead by the Special Inspection Branch (PSIB) with contracted technical assistance. These inspections are currently scheduled to be completed in 1997. In addition, DISP will support the FY97 vendor LTA and licensee inspections, as required.

Oriainatina Document: Memorandum from Gary M. Holahan and R. Lee Spessard to Ashok C. Thadani, dated October 7,1994, " Action Plan to Monitor, Review, and improve Fuel and Core Components Operating Performance" and the revision, in progress.

Reaulatorv Assessment: Core design is a fundamental component of plant safety because maintaining fuel integrity is the first principal safety barrier (i.e., fuel cladding, reactor coolant system boundary, or the containment) against serious radioactive releases. Likewise, the safety analyses must be properly performed in order to verify, in conjunction with startup tests and normal plant parameter monitoring, that the core reload design is adequate and provide assurance that the reactor can safely be operated.

Evaluation of activities that affect the quality of fuel and core components are important to ensure that safety and quality are not degraded and that the core performs as designed.

48

Current Status:

DSSA - The data acquired from the ongoing vendor inspections are being evaluated for generic impact and identification of emerging issues. The issue-driven inspection at GE, was supported by SRXB/DSSA staff and contract specialists in reload design, as was the Framatome inspection. Interaction with the j regions is ongoing to participate in region-led licensee inspections. SRXB has participated in two Region l 1 inspector counterparts meetings. DSSA is re-evaluating the action plan to better integrate and prioritize i its activities, consistent with the available FY97 TA funding. Options and recommendations for l management review are being prepared to support new emphasis on licensee inspection.

t DISP - The remaining issue-driven inspections include ABB Combustion Engineering's supply of a BWR transition core reload for WNP-2(unscheduled), and a comprehensive follow-up inspection of Siemens i Power Corporation issues, scheduled to begin 2/10/97.

l NRR Technical Contacts: E. Kendrick, SRXB, 415-2891 S. Matthews, PSIB, 415-3191 tkne opent on-site at vendor inspections (Teek 1) is allocated to appropriate fuel vendor docket #

49

)

i

! HIGH BURNUP FUEL ACTION PLAN l TAC NO. M91256 Last update: 12/19/96 Lead ,

1 NRR Division: DSSA GSI: 170 Supporting office: RES MILESTONES DATE (T/C) i

1. Issue user need letter to RES 10/93C j 2. Contracts issued by RES 03/94C

3. Schedule and coordinate meetings with foreign experimenters and 09/95C j regulatory authorities j

4. Issue Information Notice (IN 94-64) Announcing new RlA data 08/94C i l

5. Present high burnup data at water reactor safety meeting 10/94C

! 6. Schedule / coordinate industry meetings to discuss actions 10/94C s  :

7. Determine need for further generic communications 11/94C '

l

! 8. Issue letter to vendors 11/94C

9. Issue IN 94-64, Suppl.1, Providing Data and Vendor Letter 03/95C

10. RES Update NUREG-0933 on Generic issue' and Plan of Action 03/95C' 01/96C

11. Review industry (NEI) Response 09/95C

12. Assess effects on design basis accidents of reduced failure threshold for 09/95C high burnup fuel

13. Committee on the safety of nuclear installations soecialists meetina on the 09/95C transient behavior of hiah burnuo fuel

14. CNRA (OECD) Committee on nuclear regulatory activities and CSNI annual 11/95C meetings.

15. Issue ltr to NEl assessing industry actions (vendor /EPRI response to IN) 12/96T l

16. Water reactor safety information meetings (high burnup session) 10/95C core performance issues workshop 10/96C '

17. RES briefs ACRS and completes response to NRR user need letters 04/96C 02/97T

18. Complete review of available fuel transient data relevant to design basis 12/96T event

19. Develop interim acceptance criteria (e.G., Based on cladding oxide) 12/96T

20. lasue GL to define interim criteria and request post-LOCA evaluation 02/97T

21. Establish schedule for LOCA resolution and final assessment 02/97T Determine rseed for further regulatory action

• RES HAS PRioRITIZED AS GENERIC ISSUE #170 NUREG-o933.

50

i Descrintion: The action plan covers assessment of fuel performance for high burnup fuel and evaluation

] of the adequacy of srp licensing acceptance criteria.

Historical Backaround: Recent experimental data on performance of high burnup (> 50 GWD/MTU) under reactivity insertion conditions became available in mic'-1993. The unexpectedly low energy deposition (30 CAL /GM) to initiation of fuel failure in the first test rod (at 62 GWD/MTU) led to a re-evaluation of the

licensing basis assumptions in the SRP. As a result, the office of nuclear reactor regulation (NRR) was j requested to prepara an action plan, in coordination with the Office of Nuclear Regulatory Research (RES).

j l Proposed actions: After a preliminary safety assessment was performed, an action plan was developed, i

to include a user need letter to RES and the issuance of contracts to assess all aspects of the high burnup 1

fuel issue. Concurrently, meetings would be scheduled with the non-domestic experimenters and i regulatory authorities to discuss the experimental data and to assess potential consequences and i regulatory actions. Meetings with industry would be scheduled to discuss their planned actions and to i solicit cooperation with the safety evaluations. Based on a complete review of all available fuel transient i data, relevant to design basis events, NRR/RES would define acceptance criteria, establish a schedule for

! final assessment, and state need for further regulatory action.

i Oriainatina Documents: Commission Memorandum from James M. Taylor (EDO), " Reactivity Transients i and High Burnup Fuel," dated September 13,1994, including IN 94-64, ' Reactivity insertion Transient

! and Accident Limits for High Burnup Fuel,' dated August 31,1994. Commission Memorandum from

James M. Taylor, " Reactivity Transients and Fuel Damage Criteria for High Burnup Fuel," dated November j 9,1994, including an NRR safety assessment and the joint NRR/RES action plan.

i f Reaulatory Assessment There is no immediate safety issue, because of the lo;v to medium burnup in currently operating cores. Since the fuel failure threshold declines with increasing burnup, the licensing basis design acceptance criteria may need to be redefined as a function of burnup. The end product of the plan will determine the need for regulatory action and will establish and define the need for further action on extended burnup cycles and high burnup fuel issues.

Current Status: An ACRS Subcommittee Meeting on the status of RES contractor programs was held in 4/96. An NEl letter summarizing the industry position was received in April, and the opri report supporting this position was sent by NEl on 9/20/98. Currently, NRR has reviewed the documents, and is drafting a response. A commission paper on the status of the high burnup issue and planned actions has been prepared by NRR, has been reviewed by RES, and is in concurrence.

NRR Technical Contacts: Laurence Phillips, NRR/DSSA/SRXB, 415-3232 Shih Liang Wu, NRR/DSSA/SRXB, 415-3284 Edward Kendrick, NRR/DSSA/SRXB, 415-2891 RES

Contact:

Ralph Meyer, RES/ DST /RPSB, 415-6789 i

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WOLF CREEK DRAINDOWN EVENT: ACTION PLAN TAC Nos. M92635 Last Update: 12/18/96 \

i

Lead NRR Division:DSSA 5

MILESTONES DATE (T/C)

1. Draft Generic Letter 11/95(C)

.2. Issue Supplement to IN 95-03 03/96(C)

3. Complete Draft Tl/ Issue to the Regions for Comments 2/97(T) i

4. Generic Letter to be Concurred by CRGR / Letter issued 09/96(C)/

2/97(T)

5. Receive Regional Comments on Tl 04/97(T)

6. Complete Evaluation of the Responses to the Generic Letter 07/97(T) I l 7. Issue Tl 07/97(T) i 8. Complete Inspections (As necessary) 10/97(T) l Descriotion: The objective of this action plan is to collect and evaluate information from the licensees regarding plant system configurations and vulnerabilities to draindown events. A 10 CFR 50.54(f) letter 1 will be used to gather the information, and the licensees are expected to take corrective actions, as l appropriate.

I '

Historical Backaround: On September 17,1994, the Wolf Creek plant experienced loss of reactor i coolant system (RCS) inventory, while transitioning to a refueling shutdown. The event occurred when I

operators cycled a valve in the train A side of the RHR system cross-connect line following maintenance on the valve, while at the same time establishing a flow path from the RHR system, train B, to the

, refueling water storage tank for reborating train B. The failure of the reactor operating staff to adequately I control two incompatible activities resulted in transferring 9200 gallons of hot RCS water to the RWST in i 66 seconds. ,

The Wolf Creek event represents a LOCA with the potential to consequentially fail all the ECCS pumps and bypass the containment. Another important feature of this event is the short time available for i

corrective action. Based upon calculations by the licensee and the staff, it is estimated that if the i draindown had not been isolated within 3-5 minutes, net potitive suction head would have been lost for l all ECCS pumps, and core uncovery would follow in about 25-30 minutes. This event represents a PWR vulnerability which was not previously recognized.

l Prooosed Actions: Specific actions of this generic action plan are: (1) issue IN 95-03 issued January 12, j 1995; and supplement to IN 95-03 issued March 25, 1996,(2) Request all PWR licensees, via an 1 information gathering (10 CFR 50.54(f)) Generic Letter (GL), to provide information on draindown vulnerabilities and the measures they implemented to diminish the probability of a draindown. The staff i considers the proposed action as a compliance backfit issue.

i Oriainatina Document: AEOD/S95-01, " Reactor Coolant System Blowdown at Wolf Creek on September 17,1994".

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Reaulatory Assessment: The staff performed an evaluation of the probability for event initiation and of the conditional core damage probability. The value of this probability for core damage along with licensee awareness for this scenario makes the risk for continued PWR operation acceptably small.

Current Status: Information Notice iN 95-03 has been issued. Information Notice Supplement has also been issued.

NRR Technical

Contact:

M. M. Razzaque, SRXB, 415-2882 NRR Lead PM: J. C. Stone, DRPW, 415-3063

References:

• AEOD/S95-01, " Reactor Coolant System Blowdown at Wolf Creek on September 17,1994"

• IN 95-03, issued January 18,1995.

• Supplement to IN 95-03, issued Ms.rch 25,1996.

• Action Plan dated October 20,1995.

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Attachment 2 I

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i 1 GENERIC COMMUNICATION AND COMPLIANCE

.i ACTIVITIES Y

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Pag 2 No. 1 ,

01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Open Generic Communication and Compliance Activities Sorted by Lead Technical Division and Branch

! TAC Type Contact LA Comp Title Description

• • LTD - Associate Director for Projects t

• LTB - Technical Specifications Branch  ;

M91404 GL JWShapaker 1/15/97 T GL: Administrative Controls Section Line item improvement, guidance on revising the admin controls section of T.S.

M92544 GL JWShapaker 3/12/97 T GL: Design Features Technical Guidance to revise the design features Specifications section of T.S. (line item improvement)

• • LTD - Division of Engineering

• LTB - Civil Engineering and Geosciences Branch ,

M92553 LT RABenedict 12/15/96 L Investigate Impact of Failure of Certain steel framing members failed in SMRFs (During Northridge EQ) to NPP earthquake. Determine if same construction  !

Steel Structures used in other plants.  ;

M94293 GL JWShapaker 3/14/97 T GL: NRC Preliminary Findings Develop a GL to advise licensees that the use Related To The Use Of Reduced of reduced seismic criteria for temporary Seismic Criteria For Temporary conditions may involve unreviewed safety Conditions. questions and staff review may be needed.  !

M94861 IN RABenedict 12/30/96 L IN: Liner Plate Corrosion in Corroded liner might be weakened against Concrete Containment post-accident leakage. l M95688 LT TAGreene 9/30/97 T Study of The Adequacy of Enveloped After completion of contract JCN J-2354, an Response Spectrum Method IN might be issued to caution operating plant .

licensees that under certain conditions ERS  !

analysys method may not provide adequate  !

estimates of seismic response of piping ,

systems.  :

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Paga No. 2 01/09/97  :

PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT .

Open Generic Communication and Compliance Activities Sorted by Lead Technical Division and Branch i

TAC Type Contact LA Comp Title Description M95791 IN NKHunemuller 2/28/97 T Review of Generic Implications of Inform licensees regarding the possible Millstone 3 Experience with Erosion erosion of cement from porous concrete of Cement from Containment Mat subfoundations below containment basemats.

• LTB = Electrical Engineering Branch M95215 LT DLSkeen 8/1/97 T Charging / Discharging of Study and interact-with the industry group on Safety-Related AT&T Round Cell the AT&T round cell battery degradation ,

Batteries problems.

M96055 LT CVHodge 1/31/97 T GE Magne-Blast Breaker Failure Risk insight for common-mode failures M96076 LT EJBenner 12/31/96 L Cracking of Phenolics in Reactor Evaluate need for additional GC beyond an IN Trip Breakers on cracking of phenolics in reactor trip  ;

breakers i M96611 IN JRTappert 1/8/97 L IN: Improper Grounding Results in Alerts to licensees to potential problems Fire at Palo Verde concerning component grounding problems which could result in similtcaeous fires.

M96616 GL JWShapaker 1/29/97 T GL: Medium-Voltage Circuit Breaker GL to address continued breaker problems Failures because of refurbishment practices, licensee maintenance, and inadequate review of industry operating experience.

M97147 LT DLSkeen 3/1/97 T LT: Failure of Westinghouse Type Evaluate failure of breakers due to degraded DS-206 Circuit Breakers lubricant.

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e Paga No. 3 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Open Generic Communication and Compliance Activities Sorted by Lead Technical Division and Branch TAC Type Contact LA Comp Title Description M97149 IN ENFields 1/8/97 L IN 92-27, Sup 1, Thermal Induced Alerts licensees to thermally accelerated ,

Accelerated Aging and Failure of aging and failure of ITE/G0ULD relays at >

ITE/Gould Relays Used in Beaver Valley Unit 2.

Safety-Related Applications M97328 IN DLSkeen 3/15/97 T IN 95-22,Sup 1, Hardened or Supplement to IN to discuss additional area Contaminated Lubricants Cause of operating mechanism where hardened Metal-Clad Circuit Breaker Failures lubricant can cause breaker failure.

M97397 IN JRTappert 2/28/97 T IN: Potential Deficiency of Notifies licensees about information '

Electric Cable Connections obtained from aging and LOCA testing of electrical cable connections as contained in ,

the Sandia National Laboratory draft report NUREG/CR-6412.

M97436 IN DLSkeen IN: Potential Armature Binding in Contact support assembly hole slightly GE Type HGA Relays off-center in relays made between 1989-1991.

Could result in armature binding.

• LTB - Materials and Chemical Engineering Branch M95279 GL JWShapaker 3/28/97 T GL: Modification of The Extending to operating reactor licensees, on  ;

Requirements for Post-Accident voluntary basis, relaxations in PASS program ,

Sampling System requirements.

M95280 GL JWShapaker 2/14/97 T GL: Primary Water Stress Corrosion Identification of need to implement program Cracking of Control Rod Drive for assuring timely inspection of PWR vessel Mechanism And Other Vessel Head head penetrations.  :

Penetrations L

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Pagn No. 4 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Open Generic Communication and Compliance Activities ,

Sorted by Lead Technical Division and Branch TAC Type Contact LA Comp Title Description M95290 GL JWShapaker 2/28/97 T GL: Degradation of Steam Generator Identification of steam generator internals Internals degradation mechanisms based on foreign .

reactor operating experience, M95373 GL JWShapaker 3/14/97 T GL: Implementation of App. VIII of Discusses the need for lecensees to adopt the  ;

Sec XI of The 1995 Edition of The Appendix VIII to improve the quality and .

ASME Boiler And Pressure Vessel confidence level of inservice inspections.

Code  :

f M95444 LT TAGreene 6/15/97 T Lead Technical Review - Induction Cracking has been found in several utilities' Heat Stress Improvement for austentic stainless steel piping which had ,

Stainless Steel. Piping been subjected to IHSI in the 1980's . Staff  !

concerns include that IHSI may not have been  !

properly applied.

M96401 GL JWShapaker 2/28/97 T GL: Steam Generator Tube Inspection Informs licensees of the importance of Techniques performing steam generator tube inservice  ;

inspections using qualified techniques and I

. requests that licensees implement described  ;

actions. j M97230 GL JWShapaker 6/30/97 T GL: Quality Assurance Programs for Requests addressees to provide information  !

Safety-Related Coatings concerning QA aspects of their coatings f monitoring program and containment sump flow  !

models. ,

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Page No. 5 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Open Generic Communication and Compliance Activities Sorted by Lead Technical Division and Branch TAC Type Contact LA Comp Title Description M97329 IN EJBenner 2/7/97 T IN: Degradation in U-Bend Regions Informs licensees of performing S/G tube of Steam Generator Tubes inspections for detection of degradation in U-bend region.

H97395 IN TJCarter 1/15/97 T IN: Cracking of BWR Jet Pump Riser Cracks in the jet pump riser elbow have not Elbow been observed previously.

'TB - Mechanical Engineering Branch Pi95443 IN WFBurton 1/31/97 T IN: Thermal Fatigue Cracking In Alerts licensees an event of weld crack on Residual Heat Removal Lines safety injection line at Sequoyah.

M96073 IN EJBenner 1/31/97 T IN: Concerns with Dry Cask Loading Alerts licensees to several identified and Unloading Procedures problems with procedures for the loading and  ;

unloading of spent fuel storage casks.

M96354 LT NKHunemuller Containment Recirculation Spray and Millstone 3 determined that the containment Quench Spray Piping Outside Design recirculation spray and quench spray piping Basis and supports could be subjected to higher accident temperatures than those previously assumed in the design basis.

M96614 LT TKoshy 2/20/97 T LPSI Pump Mission Time When the RCS pressure remains higher than  ;

LPSI injection head, the pumps may be  !

required to run for long durations with ~

minimum flow. It appears that there is no demonstrated evidence to ensure LPSI pump capability for the require mission time.

I

Paga No. 6 i

01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT -

Open Generic Communication and Compliance Activities Sorted by Lead Technical Division and Branch j LA Comp Title Description TAC Type Contact M96714 IN TKoshy 2/18/97 T IN: Steam Line Rupture at Oconee Informs licensees the event that occurred at Ocoree Unit 2 on 9/24/96. In this event, a Unit 2 heater drain line ruptured due to waterhammer, and caused significant injury to members- of plant staff.

M96917 IN WFBurton 1/31/97 T IN: NRC Inspection of Completion of Alerts licensees to lessons learned from the Generic Letter 89-10 MOV Programs staff's GL 89-10 close-out inspections.

LT: Target Rock Two-Stage SRV Consider Issuing an information notice when M97327 LT CDPetrone BWR owners group comes to a conclusion  ;

Setpoint Drift regarding the cause of the Target Rock two-stage SRV setpoint drift.

i

• • LTD - Division of Inspection and Support Programs i

• LTB = Special Inspections Branch IN to discuss problems with cotter pins, M97298 IN DLSkeen 2/28/97 T IN: Failures of GE Magne Blast '

Breakers contacts, trip cranks, and trip levers.

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. t Paga No. 7 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT i Open Generic Communication and Compliance Activities Sorted by Lead Technical Division and Branch LA Comp Title Description TAC Type Contact i

• • LTD - Division of Reactor Controls and Human Factors i

• LTB - Operator Licensing Branch Notify licensee of NRC's decision to change '

M94840 GL JWShapaker 1/31/97 T GL: Changes in The Operator Licensing Program and Issuance of the operator licensing process by giving i Rev. 8 of NUREG-1021 licensees the opportunity to directly participate in the preparation of draft written examinations and operating tests for NRC use.

• • LTD - Division of Reactor Program Management

• LTB - Emergency Preparedness and Radiation Protection Branch Issues IN to report the results of Temporary M96916 IN MKotzalas IN: Licensee Offsite Communication Capabilities Instruction 2515/131 on offsite communication capability.

• LTB = Events Assessment and Generic Communications Branch Reducing reporting requirements to the M91544 GL JWShapaker 1/31/97 T GL: Defining Info in Monthly minimum needed by the staff (part of RRG).

Operating Report Required by Tech Specs IN: Distribution of AE00 Study Information Notice authorized as an M96915 IN SSKoenick 2/13/97 T appropriate method of alerting licensees of

" Assessment of Spent Fuel Cooling" AE00's study. NUREG will be referenced in IN.

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Paga No. 8 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT '

Open Generic Communication and Compliance Activities

~ Sorted by Lead Technical Division and Branch  ;

TAC Type Contact LA Comp Title Description

• • LTD - Division.of Systems Safety and Analysis  !

• LTB - Analytical Support Group ,

M96947 LT TAGreene LT : Possible Computer Code Identical computer models launched from ,

Platform Dependency different personal computer platforms can i result in different calculations. i

• LTB - Containment Systems and Severe Accident Branch M96537 GL JWShapaker 2/22/97 T GL: Assurance of Sufficient NPSH Notifies licensees about a safety-significant i for ECCS and Containment Heat issue that could affect the ability for j Removal System Pumps long-term core cooling.and containment heat removal under accident conditions and which .

has generic implications.  !

M97146 BL JWShapaker 2/18/97 T BL: Degradation of ECC Notifies addressees about the potential i Recirculation Following a LOCA due safety impact of foreign material in sumps to Foreign Material in the and suppression pools, which could render Containment s2rety-related equipment inoperable. ,

M97297 LT EJBenner 11/30/97 T LT: Errors in Containment Code Identify generic actions necessary as a y Analysis result of potential errors in Oconee's  :

Bulletin 80-04 response.  !

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Pags No. 9 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Open Generic Communication ano Compliance Activities Sorted by Lead Technical Division and Branch TAC Type Contact LA Comp Title Description '

• LTB - Plant Systems Branch M80296 LT TAGreene 9/30/97 T Generic Communications - Assessment Development of staff NUREG or other of Turbine Failure at Vandellos 1 publication to document. turbine building fire issues for U.S. plants in light of Vandellos fi re.

M91323 LT NKHunemuller 2/28/97 T Reactor Water Cleanup (RWCU) Study Review of the effects of an unisolated RWCU in Response to ACRS Concern break at several BWR's. Result of ACRS concerns during the review of the ABWR M93335 LT WFBurton 4/30/97 T Main Control Room Envelope Use improved methodology to verify the Unfiltered Inleakage effects of potential inleakage rates on compliance with radiation and toxic gas exposure limits inside the main control room.

M95871 IN TAGreene 2/19/97 T IN: Emergency Lighting Issues Develop IN to alert licensees to potential problems regarding emergency lighting for plant areas needed for operation of post-fire safe shutdown equipment and in the access and egress routes.

M96502 LT CDPetrone 12/30/96 L Potential for Air Regulator Determine if industry response to IN 88-24 Failures to Overpressurized and GL 91-15 is adequate, in light of 9/6/96 Safety-Related SOVs Millstone 3 discovery of susceptible SOVs. ,

M96912 LT SSKoenick 1/22/97 T LT: Potential Generic Concern with Farley - Failure of numerous pre-action regard to Fire Protection Actuation sprinklers in fire protection systems System providing fire protection service to safety-related system components.

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I Paga No. 10 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY-STATUS REPORT Open Generic Communication end Compliance Activities -

Sorted by Lead Technical Division and Branch TAC Type Contact LA Camp Title Description

. M96913 IN JRTappert 1/31/97 T IN 92-18, Sup 1, " Potential for Updates IN 92-18 with examples of Loss of Remote Shutdown Capability noncompliance and civil penalties.

during a Control Room Fire" M97151 IN TAGreene 2/15/97 T Ih:~ Inadequate or Inappropriate To provide examples of the fire watches used Fire Protection Compensatory as compensatory measures for Appendix R 1 Neasures deficiencies.

t M97207 IN TAGreene 1/6/97 L IN 91-85, Rev 1, " Potential To clarify that the failure of the ]

Failures of Thermastatic Cantrol thermostatic control valve for the DG jacket Valves for DG Jacket Cooling Water" cooling water at Catawba Nuclear Station occurred beyond its normal service life.

M97253 IN TJCarter 2/19/97 T IN: Misapplication of Internal Pipe Millstone 3 reported that pipe coating Coating material had come loose and could cause heat exchanger.inoperability.

3 M97299 GL JWShapaker 3/28/97 T GL: Spent Fuel Pool Compliance Requests licensees to describe their spent -

Activities fuel pool offload practices, temperature limits and bases, and decay heat removal redundancy and include the information in the FSAR.

• LTB = Reactor Systems Branch M80326 LT SSKoenick 1/31/97 T Accumulation of Volume Control Tank Not a new issue, there have been several

• Cover Gass in ECCS Piping Connected generic communications already issued. SRX8 to the Charging System. would like to close this cat by_meno.

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i Paga No.- 11 01/09/97 i PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT.

Open Generic Communication and Compliance Activities Sorted by Lead Technical Division and Branch TAC Type Contact LA Comp Title Description M92635 GL' JWShapaker 2/28/97 T GL: Reactor Coolant Inventory Loss Loss of ECCS function due to steam voiding in ,

and Potential Loss of Emergency RWST line to suction of ECCS pumps due to. '

Mitigation Functions While Shutdown loss of RCS inventory in Mode 4 (Wolf Creek).

M94565 LT DLSkeen 7/31/97 T Slow Scram Solenoid Pilot Valves Scram solenoid pilot valves with viton Caused by Viton Diaphrages- diaphrages showir.g degraded scram times within 6-8 months. Currently tracking ,

licensee response to RRG recommendations.  !

i M95278 GL JWShapaker 3/14/97 T GL: Use of Thermal-Hydraulic Codes Discusses the fac that a computer code has for Licensing Applications been developed anc assessed primarily with i NRC funds does not per se mean that it is acceptable as a licensing code.

M96191 IN RABenedict 12/31/96 L IN: Plant Specific E0Ps Contain Alerts licensees the problem with ICS/FWCS Inadequate Technical Info to interactions. ~The proposed IN was prompted j Accomplish Timely and Effectively by the ANO-1 5/19/96 event.

Feeding of OTSG M96192 IN WFBurton 1/31/97 T IN: ECCS Throttle Valves May High differential pressure across ECCS ,

Degrade Due To Cavitation Induced throttle valves during LOCA could cause pump l Erosion During LOCA runout flow and subsequent ECCS pump damage j i

M96355 LT SSKoenick 1/15/97 T Concerns Regarding Siemens Large Changes to large break ECCS model may have i Break LOCA ECCS Evaluation Model resulted in significant changes in calculated  :

peak clad temperatures for some plants.

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Paga No. 12

' 01/09/97 ,

PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT  !

Open Generic Communication and Compliance Activities

- Sorted by Lead Technical Division and Branch ,

t TAC Type Contact LA Comp Title Description M96615 LT TKoshy 1/30/97 T Boron Precipitation in B&W Reactors Design bases concern on active means of  ;

preventing boron precipitation following a

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LOCA.

M96914 IN EJBenner 1/3/97 L IN: Inadequate MSSV Setpoints due Informs licensees of potential steam to Neglecting the Dynamic Pressure generator overpressure during certain design i Loss between the SG and the MSSVs basis events.

M96948 IN SSKoenick 1/19/97 T IN: Reporting of Changes in the IN discusses reporting requirements of 10 CFR Large Break LOCA ECCS Evaluation 50.46(a)(3)(1), focusing on licensees' ,

Models responsibility for change in calculated peak fuel cladding temperature greater-than 50 F.

M96961 IN CDPetrone 2/28/97 T IN: Extended Operation in Extended use of the suppression pool cooling Suppression Pool Cooling Mode mode of RHR may be outside the design basis analysis assumptions and may require 50.59 review.

M97150 LT TJCarter 1/15/97 T LT: Evaluate Postulated Concern A potential scenario not adequately addressed During Cool Down of Reactor by E0Ps was discovered during an inspection Following a Reactor Shutdown after at Cooper. i ATWS Event 4 M97331 BL JWShapaker 3/28/97 T BL: Inadequate Procedural Guidance Requests PWR licensees to take action to -

during S/D and Site Specific assure that there is adequate procedural Vulnerabilities due to Gas guidance during shutdown operation and that Accumulation gas accumulation vulnerabilities are  !

identified, and actions are taken to limit or preclude adverse system performance, i t

Page No. 13 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Open Generic Communication and Compliance Activities Sorted by Lead Technical Division and Branch ,

TAC Type Contact LA Comp Title Description M97396 BL JWShapaker 3/28/97 T BL 96-01, Sup 1, Control Rod Informs addressees of issues concerning Insertion Problems incomplete control rod insertion due to distortion of thimble tubes.

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Pagn No. 1 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Open Long Tern Followup Type i Generic Communication and Compliance Activities Sorted by Lead Technical Division and Branch TAC Contact LA Comp Title Description

• • LTD - Division of Engineering

• LTB - Civil Engineering and Geosciences Branch .

M92553 RABenedict 12/15/96 L Investigate Impact of Failure of Certain steel framing members failed in SMRFs (During Northridge EQ) to NPP earthquake. Determine if same construction used Steel Structures in other plants.

M95688 TAGreene 9/30/97 T Study of The Adequacy of Enveloped After completion of contract JCN J-2354, an IN Response Spectrum Method might be issued to caution operating plant licensees that under certain conditions ERS analysys method may not provide adequate estimates ,

of seismic response of piping systems.

• LTB - Electrical Engineering Branch M95215 DLSkeen 8/1/97 T Charging / Discharging of Study and interact with the industry group on the Safety-Related AT&T Round Cell AT&T round cell battery degradation problems.

Batteries M96055 CVHodge 1/31/97 T GE Magne-Blast Breaker Failure Risk insight for common-mode failures M96076 EJBenner 12/31/96 L Cracking of Phenolics in Reactor Evaluate need for additional GC beyond an IN on Trip Breakers cracking of phenolics in reactor trip breakers M97147 DLSkeen 3/1/97 T LT: Failure of Westinghouse Type Evaluate failure of breakers due to degraded DS-206 Circuit Breakers lubricant.

Paga No. 2

! 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Open Long Tern Followup Type l Generic Communication and Compliance Activities  !

Sorted by Lead Technical Division and Branch 1

! TAC Contact LA Comp Title Description i

• LTB = Materials and Chemical Engineering Branch M95444 TAGreene 6/15/97 T Lead Technical Review - Induction Cracking has been found in several utilities' .

Heat Stress Improvement for austentic stainless steel piping which had been  !

Stainless Steel Piping subjected to IHSI in the 1980's . Staff concerns  !

include that IHSI may not have been properly

' applied.

• LTB - Mechanical Engineering Branch M96354 NKHunemuller Containment Recirculation Spray and Millstone 3 determined that the containment ,

Quench Spray Piping Outside Design recirculation spray and quench spray piping and Basis supports could be subjected to higher accident temperatures than those previously assumed in the design basis.

L M96614 TKoshy 2/20/97 T LPSI Pump Mission Time When the RCS pressure remains higher than LPSI injection head, the pumps may be required to run for long durations with minimum flow. It appears that there is no demonstrated evidence to ensure LPSI pump capability for the require mission time.

M97327 CDPetrone LT: Target Rock Two-Stage SRV Consider Issuing an information notice when BWR Setpoint Drift owners group comes to a conclusion regarding the cause of the Target Rock two-stage SRV setpoint drift.

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Paga No. 3 ,

01/09/97  !

PUBLIC JANUARY 1997 D' RECTOR'S MONTHLY STATUS REPORT Open Long Term Followup Type Generic Communication and Compliance Activities Sorted by Lead Technical Division and Branch TAC Contact LA Comp Title Description

• • LTD = Division of Systems Safety and Analysis

• LTB - Analytical Support Group .

M96947 TAGreene LT : Possible Computer Code Identical computer models launched from different Platform Dependency personal computer platforms can result in  !

different calculations.

• LTB - Containment Systems and Severe Accident Branch M97297 EJBenner 11/30/97 T LT: Errors in Containment Code Identify generic actions necessary as a result of Analysis potential errors in Oconee'sBulletin 80-04 .

response.  ;

• LTB - Plant Systems Branch  !

M80296 TAGreene 9/30/97 T Generic Communications - Assessment Development of staff NUREG or other publication to of Turbine Failure at Vandellos I document turbine building fire issues for U.S.

plants in light of Vandellos fire. j M91323 NKHunemuller 2/28/97 T Reactor Water Cleanup (RWCU) Study Review of the effects of an-unisclated RWCU break in Response to ACRS Concern at several BWR's. Result of ACRS concerns during ,

the review of the ABWR i M93335 WFBurton 4/30/97 T Main Control Room Envelope Use improved methodology to verify the effects of Unfiltered Inleakage potential inleakage rates on compliance with- .

radiation and toxic gas exposure limits inside the  !

main control room.

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Pags No. 4 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Open Long Tern Followup Type ,

Generic Communication and Compliance Activities  !

Sorted by Lead Technical Division and Branch TAC Contact LA Comp Title Description M96502 CDPetrone 12/30/96 L Potential for Air Regulator Determine if industry response to IN 88-24 and GL Failures to Overpressurized 91-15 is adequate, in light of 9/6/96 Millstone 3 Safety-Related SOVs discovery of susceptible SOVs.

M96912 SSKoenick 1/22/97 T LT: Potential Generic Concern with F&rley - Failure of numerous pre-action sprinklers regard to Fire Protection Actuation in fire protection systems providing fire System protection service to safety-related system  !

components.

l

• LTB = Reactor Systems Branch M80326 SSKccr.fck 1/31/97 T Accumulation of Volume Control Tank Not a new issue, there have been several generic '

Cover Gass in ECCS Piping Connected communications already issued. SRXB would like to to the Charging System. close this out by meno.

M94565 DLSkeen 7/31/97 T Slow Scram Solenoid Pilot Valves Scram solenoid pilot valves with viton diaphrages ft Caused by Viton Diaphrages showing degraded scram times within 6-8 months.

Currently tracking licensee response to RRG recommendations. ,

M96355 SSKoenick _1/15/97 T Concerns Regarding Siemens Large Changes to large break ECCS model may have Break LOCA ECCS Evaluation Model resulted in significant changes in calculated peak  ;

clad temperatures for some plants.

M96615 TKoshy 1/30/97 T Boron Precipitation in B&W Reactors Design bases concern on active means of preventing boron precipitation following a LOCA. ,

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Ptga No. 5 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT i Open Long Tern Followup Type Generic Communication and Compliance Activities Sorted by Lead Technical Division and Branch  ;

TAC Contact LA Comp Title Description M97150 TJCarter 1/15/97 T LT: Evaluate Postulated Concern A potential scenario not adequately addressed by During Cool Down of Reactor E0Ps was discovered during an inspection at Following a Reactor Shutdown after Cooper.  !

ATWS Event l P

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t L

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Paga No. 1 i 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Added l Since the Last Public Report (October 1996)

TAC Type Contact Tech Branch LA Comp Title Reason Added  !

i M95791 IN NKHunemuller Civil 2/28/97 T Review of Generic The EAP authorized development of IN at i Engineering and Implications of Millstone its 11/5/96 meeting. -

Geosciences 3 Experience with Erosion

• Branch of Cement from Containment Mat M96702 TJCarter Reactor Systems 10/29/96 C IN: Fuel Analysys The proposed IN was canceled per Branch Discrepancy LPhillips' request (10/18/% e-mail to TJC). The EAP concurred with this request. at its 10/22/96 meeting.

t M96714 IN TKoshy Mechanical 2/18/97 T IN: Steam Line Rupture at The EAP authorized development of IN at Engineering Oconee Unit 2 its 10/8/96 meeting.

Branch  !

M96912 LT SSKoenick Plant Systems 1/22/97 T LT: Potential Generic The EAP authorized LT follow-up of this Branch Concern with regard to issue at its 10/22/96 meeting.

Fire Protection Actuation System M96913 IN JRTappert Plant Systems 1/31/97 T IN 92-18, Sup 1, The EAP authorized development of IN at Branch " Potential for loss of its 10/22/96 meeting Remote Shutdown Capability during a  !

Control Room Fire" ,

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Page No. 2 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Added Since the Last Public Report (October 1996) i TAC Type Contact Tech Branch LA Comp Title Reason Added ,

M96914 IN EJBenner Reactor Systems 1/3/97 L IN: Inadequate MSSV The EAP authorized development of IN at Branch Setpoints due to its 10/22/96 meeting Neglecting the Dynamic Pressure Loss between the SG and the MSSVs M96915 IN SSKoenick Events 2/13/97 T IN: Distribution of AE00 The EAP authorized development of IN at Assessment and Study " Assessment of' its 10/22/96 meeting Generic Spent Fuel Cooling" '

Communications Branch M96916 IN MKotzalas Emergency IN: Licensee Offsite The EAP authorized development of IN at Preparedness Communication its 10/22/96 meeting  ;

and Radiation Capabilities i Protection l Branch M96917 IN WFBurton Mechanical 1/31/97 T IN: NRC Inspection of The EAP authorized development of IN at  !

Engineering Completion of Generic its 10/22/96 meeting Branch Letter 89-10 MOV Programs M96947 LT TAGreene Analytical LT : Possible Computer The EAP authorized LT follow-up of this  ;

Support Group Code Platform Dependency issue at its 10/29/96 meeting.

M96948 IN SSKoenick Reactor Systems 1/19/97 T IN: Reporting of Changes The EAP authorized development of IN at Branch in the large Break LOCA its 10/29/96 meeting.

ECCS Evaluation Models l

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Pagm No. 3 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT i Generic Comm!nication and Compliance Activities Added Since the Last Public Report (October 19%)  ;

TAC Type Contact Tech Branch LA Comp Title Reason Added M96961 IN CDPetrone P.eactor Systems 2/28/97 T IN: Extended Operation in The EAP authorized development of IN at Branch Suppression Pool Cooling its 11/26/96 meeting.

Mode M97146 BL JWShapaker Containment 2/18/97 T BL: Degradation of ECC The EAP authorized development of BL at  !

Systems and Recirculation Following a its 11/5/96 meeting.

Severe Accident LOCA due to Foreign  !

Branch Material in the i Containment  ;

l' M97147 LT DLSkeen Electrical 3/1/97 T LT: Failure of The EAP authorized long-term follow up Engineering Westinghouse Type DS-206 of this issue at its 11/5/96 meeting.  !

l Branch Circuit Breakers M97149 IN ENFields Electrical 1/8/97 L IN 92-27, Sup 1, Thermal The EAP authorized development of IN at l Engineering Induced Accelerated Aging its 11/5/96 meeting.  !

Branch and Failure of ITE/Gould i Relays Used in Safety-Related i Applications  !

M97150 LT TJCarter Reactor Systems 1/15/97 T LT: Evaluate Postulated The EAP authorized long-term follow up Branch Concern During Cool Down of this issue at its 11/5/96 meeting. -

of Reactor Following a ,

Reactor Shutdown after ATWS Event  :

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Paga No. 4 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Added Since the Last Public Report (October 1996)

TAC Type Contact Tech Branch LA Ccap Title Reason Added M97151 IN TAGreene Plant Syster 2/15/97 T IN: Inadequate or The EAP authorized development of IN at Branch Inappropriate Fire its 11/5/96 meeting.

Protection Compensatory Measures M97207 IN TAGreene Plant Syrtens 1/6/97 L IN 91-85, Rev 1, 11/13/96 - AEChaffee authorized Branch " Potential Failures of development of IN.

Thermostatic Control Valves for DG Jacket Cooling Water" M97230- GL JWShapaker Materials and 6/30/97 T .GL: Quality Assurance The EAP authorized development of GL at Chemical Programs for its 11/19/96 meeting.

Engineering Safety-Related Coatings Branch M97253 IN TJCarter Plant Systems 2/19/97 T IN: Misapplication of The EAP authorized development of IN at Branch Internal Pipe Coating its 11/19/96 meeting.

M97297 LT EJBenner Containment 11/30/97 T LT: Errors in Containment The EAD authorized LT followup of this Systems and Code Analysis issue at its 11/26/96 meeting.

Severe Accident Branch

. M97298 IN DLSkeen Special 2/28/97 T IN: Failures of GE Magne The EAP authorized development of IN at Inspections Blast Breakers its 11/26/96 meeting.

Branch I

i

Pags No. 5 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Added Since the Last Public Report (October 1996)

TAC Type Contact Tech Branch LA Comp Title Reason Added M97299 GL JWShapaker Plant Systems 3/28/97 T GL: Spent Fuel Pool The EAP authorized development of GL at Branch Compliance Activities its 11/26/96 meeting.

M97327 LT CDPetrone Mechanical LT: Target Rock Two-Stage The EAP authorized LT follow-up of this Engineering SRV Setpoint Drift issue at its 12/3/96 meeting Branch M97328 IN DLSkeen Electrical 3/15/97 T IN 95-22,Sup 1, Hardened The EAP authorized development of IN at Engineering or Contaminated its 12/3/96 meeting.

Branch Lubricants Cause Metal-Clad Circuit Breaker Failures M97329 IN EJBenner Materials and 2/7/97 T IN: Degradation in U-Bend The EAP authorized development of IN at Chemical Regions of Steam its 12/3/96 meeting.

Engineering Generator Tubes Branch M97331 BL JWShapaker Reactor Systems 3/28/97 T BL: Inadequate Procedural The EAP authorized development of BL at Branch Guidance during S/D and its 12/3/% meeting.

Site Specific Vulnerabilities due to Gas Accumulation M97395 IN TJCarter Materials and 1/15/97 T IN: Cracking of BWR Jet The EAP authorized development of IN at Chemical Pump Riser Elbow its 12/10/96 meeting.

Engineering Branch

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Pagm No. 6 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Added Since the Last Public Report (October 1996)

TAC Type Contact Tech Branch LA Comp Title Reason Added M97396 BL JWShapaker Reactor Systems 3/28/97 T BL 96-01, Sup 1, Control The EAP authorized development of BL Branch Rod Insertion Problems supplement at its 12/10/96 meeting.

M97397 IN JRTappert Electrical 2/28/97 T IN: Potential Deficiency The EAP authorized development of IN at Engineering of Electric Cable its 12/10/96 meeting. l Branch Connections M97436 IN DLSkeen Electrical IN: Potential Armature The EAP authorized development of IN at Engineering Binding in GE Type HGA its 12/17/96 meting.

Branch Relays i

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Pags No. <

1 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT I Generic Communication and Compliance Activities Added Since the June 30, 1996 TAC Type Contact Tech Branch TR Comp Title Reason Added t

M95444 LT TAGreene Materials and 12/31/97 Lead Technical Review - Per EMCB's request, AEC authorized  :

Chemical Induction Heat Stress long-term follow up of this issue on Engineering Improve.nent for Stainless 5/29/96.  !

Branch Steel Piping i M95791 IN NKHunemuller Civil 01/31/97 Review of Generic The EAP authorized development of IN at Engineering and Implications of Millstone its 11/5/96 meeting.

Geosciences 3 Experience with Erosion Branch of Cement from ,

Containment Mat M95871 IN TAGreene Plant Systems --/--/-- IN: Emergency Lighting The EAP authorized development of IN at Branch Issues its 7/2/96 meeting. t M96055 LT CVHodge Electrical 11/11/11 GE Magne-Blast Breaker 7/23/96: The EAP authorized a long-tenn i Engineering Failure follow up for this issue.

Branch M96073 IN EJBenner Mechanical --/--/-- IN: Concerns with Dry The EAP authorized development of IN Engineering Cask Loading and at its 7/16/96 meeting. .

Branch Unloading Procedures M96074 AL TAGreene Materials and 10/26/97 AL: Notice of Technical This GC has been changed to an AL. per Chemical Guidance Issued in USNRC e-mail from JWS to PXW ,10/2/%.

Engineering Inspection Manual Branch Regarding 10 CFR 50.55a/ASME Code issues r

Pags No. 2 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Added Since the June 30,19%

TAC Type Contact Tech Branch TR Comp Title Reason Added M96076 LT EJBenner Electrical 11/11/11 Cracking of Phenolics in The EAP authorized a long-term follow Engineering Reactor Trip Breakers up for this issue (beyond an IN) at its Branch 7/16/96 meeting..

M96191 IN RABenedict Reactor Systems --/--/-- IN: Plant Specific E0Ps The EAP authorized development of IN at Branch Contain Inadequate its 7/23/96 meeting.

Technical Info to Accomplish Timely and Effectively Feeding of OTSG M96192 IN WFBurton Reactor Systems --/--/-- IN: ECCS Throttle Valves The EAP authorized development of IN at Branch May Degrade Due To its 7/23/96 meeting.

Cavitation Induced Erosion During LOCA M96196 RABenedict 07/30/96 P IN: Main Steam Safety This TAC was inadvertently opened. This Valve Failure To Reseat TAC is the same as M95686.

Caused By An Improperly Installed Release Nut

-M96354 LT NKHunemuller Mechanical --/--/-- Containment Recirculation The EAP authorized long-term followup Engineering Spray and Quench Spray for this issue at its 8/20/96 meeting.

Branch Piping Outside Design Basis

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Paga No. 3 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Added Since the June 30, 1996 TAC Type Contact Tech Branch TR Comp Title Reason Added M96355 LT SSKoenick Reactor Systems --/--/-- Concerns Regarding The EAP authorized long-term followup Branch Siemens Large Break LOCA for this issue at its 8/20/96 meeting.

ECCS Evaluation Model M96401 GL JWShapaker Materials and --/--/-- GL: Steam Generator Tube The EAP authorized development of GL at ;

Chemical Inspection Techniques its 8/27/96 meeting.

Engineering Branch M96502 LT CDPetrone Plan'c Systems --/--/-- Potential for Air The EAP authorized LT follow-up of this Branch Regulator Failures to issue at its 9/10/96 meeting..

Overpressurized Safety-Related SOVs M96537 GL JWShapaker Containment 12/30/97 GL: Assurance of The EAP authorized development of GL at Systems and Sufficient NPSH for ECCS its 9/17/96 meeting.

Severe Accident and Containment Heat Branch Removal Systeai Pumps M96611 IN JRTappert Electrical 12/30/96 IN: Improper Grounding IN 97-01 issued 1/8/97.

Engineering Results in Fire at Palo Branch Verde M96614 LT TKoshy Mechanical 09/30/97 LPSI Pump Mission Time The EAP authorized LT follow-up of this Engineering issue at its 9/24/96 meeting.

Branch

Paga No. 4 ,

01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Added i Since the June 30, 1996 TAC Type Contact Tech Branch TR Comp Title Reason Added r M96615 LT TKoshy Reactor Systems 09/30/97 Boron Precipitation in The EAP authorized LT follow-up of this Branch B&W Reactors issue at its 9/24/96 meeting. -

M96616 GL JWShapaker Electrical 11/11/11 GL: Medium-Voltage Authorized development of GL by RLD, L Engineering Circuit Breaker Failures acting for AEC, on 9/26/96.

Branch M96702 TJCarter Reactor Systems 10/29/96 P IN: Fuel Analysys The proposed IN was canceled per  ;

Branch Discrepancy LPhillips' request (10/18/96 e-mail to '

TJC). The EAP concurred with this request. at its 10/22/96 meeting. '

M96714 IN TKoshy Mechanical --/--/-- IN: Steam Line Rupture at The EAP authorized development of IN at Engineering Oconee Unit 2 its 10/8/96 meeting.

Branch M96912 LT SSKoenick Plant Systems 04/04/97 LT: Potential Generic The EAP authorized LT follow-up of this Branch Concern with regard to issue at its 10/22/96 meeting.

Fire Protection Actuation  !

System M96913 IN JRTappert Plant Systems 12/31/96 IN 92-18, Sup 1, The EAP authorized development of IN at Branch " Potential for loss of its 10/22/96 meeting Remote Shutdown Capability during a Control Room Fire"  !

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i Paga No. 5 01/09/97  !

PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Added 1 Since the June 30, 1996 -

TAC Type Contact Tech Branch TR Comp Title Reason Added  :

M96914 IN EJBenner Reactor Systems 02/28/97 IN: Inadequate MSSV The EAP authorized development of IN at i Branch Setpoints due to its 10/22/96 meeting Neglecting the Dynamic Pressure Loss between the SG and the MSSVs M96915 IN SSKoenick Events --/--/-- IN: Distribution of AEOD The EAP authori7cd development of IN at  !

Assessment and Study " Assessment of its 10/22/96 meeting Generic Spent Fuel Cooling" l Communications  !

Branch i r

M96916 IN MKotzalas Emergency 11/29/96 IN: Licensee Offsite The EAP authorized development of IN at  !

Preparedness Communication its 10/22/96 meeting '

and Radiation Capabilities Protection Branch

! M96917 IN WFBurton Mechanical --/--/-- IN: NRC Inspection of The EAP authorized development of IN at  !

Engineering Completion of Generic its 10/22/96 meeting )

Branch Letter 89-10 MOV Programs , ,

M96947 LT TAGreene Analytical 03/01/97 LT : Possible Computer The EAP authorized LT follow-up of this Support Group Code Platform Dependency issue at its 10/29/96 meeting.

M96948 IN SSKoenick Reactor Systems 03/30/97 IN: Reporti:'g of Changes The EAP authorized development of IN at i Branch in the Large Break LOCA its 10/29/96 meeting.

4 ECCS Evaluation Models i

1 i

Page No. 6 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Added Since the June 30, 1996 TAC Type Contact Tech Branch TR Comp Title Reason Added M96961 IN CDPetrone Reactor Systems --/--/-- IN: Extended Operation in The EAP authorized development of IN at Branch Suppression Pool Cooling its 11/26/96 meeting.

Mode M97146 BL JWShapaker Containment 03/31/97 BL: Degradation of ECC The EAP authorized development of BL at Systems and Recirculation Following a its 11/5/96 meeting.

Severe Accident LOCA due to Foreign Branch Material'in the Containment M97147 LT DLSkeen Electrical --/--/-- LT: Failure of The EAP authorized long-term follow up Engineering Westinghouse Type DS-206 of this issue at its 11/5/% meeting.

Branch Circuit Breakers M97149 IN ENFields Electrical --/--/-- IN 92-27, Sup 1, Thermal The EAP authorized development of IN at Engineering Induced Accelerated Aging its 11/5/% meeting.

Branch and Failure of ITE/Gould Relays Used in Safety-Related Applications M97150 LT TJCarter Reactor Systems --/--/-- LT: Evaluate Postulated The EAP authorized long-term follow up Branch Concern During Cool Down of this issue at its 11/5/% meeting.

of Reactor Following a Reactor Shutdown after ATWS Event

Pagn No. 7 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Added .

Since the June 30, 1996 TAC Type Contact Tech Branch TR Comp Title Reason Added M97151 IN TAGreene Plant Systems 02/15/97 IN: Inadequate or The EAP authorized development of IN at Branch Inappropriate Fire its 11/5/96 meeting.

Protection Compensatory Measures t M97207 IN TAGreene Plant Systems 01/06/97 IN 91-85, Rev 1, 11/13/96 - AEChaffee authorized Branch " Potential Failures of development of IN.

Thermostatic Control ,

Valves for DG Jacket Cooling Water" M97230 GL JWShapaker Materials and 05/31/97 GL: Quality Assurance The EAP authorized development of GL at Chemical Programs for its 11/19/96 meeting.

Engineering Safety-Related Coatings Branch M97253 IN TJCarter Plant Systems 02/28/97 IN: Misapplication of The EAP authorized development of IN at Branch Internal Pipe Coating its 11/19/96 meeting.

M97297 LT EJBenner Containment --/--/-- LT: Errors in Containment The EAP authorized LT followup of this Systems and Code Analysis issue at its 11/26/96 meeting.

Severe Accident Branch M97298 IN DLSkeen Special 02/15/97 IN: Failures of GE Magne The EAP authorized development of IN at Inspections Blast Breakers its 11/26/96 meeting.

Branch i

l Page No. 8 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Comunication and Compliance Activities Added Since the June 30, 1996 TAC Type Contact Tech Branch TR Comp Title Reason Added M97299 GL JWShapaker Plant Systems --/-/-- GL: Spent Fuel Pool The EAP authorized development of GL at i Branch Compliance Activities its 11/26/96 meeting.

M97327 LT CDPetrone Mechanical --/--/-- LT: Target Rock Two-Stage The EAP authorized LT follow-up of this  !

Engineering SRV Setpoint Drift issue at its 12/3/96 meeting Branch M97328 IN DLSkeen Electrical 03/15/97 IN 95-22,Sup 1, Hardened The EAP authorized development of IN at Engineering or Contaminated its 12/3/96 meeting.  ;

Branch Lubricants Cause Metal-Clad Circuit i Breaker Failures M97329 IN EJBenner Materials and 04/28/97 IN: Degradation in U-Bend The EAP authorized development of IN at Chemical Regions of Steam its 12/3/96 meeting.  !

Engineering Generator Tubes Branch M97331 BL JWShapaker Reactor Systems 06/30/97 BL: Inadequate Procedural The EAP authorized development of BL at Branch Guidance during S/D and its 12/3/96 meeting.

Site Specific .t Vulnerabilities due to Gas Accumulation M97395 IN TJCarter Materials and 10/03/97 IN: Cracking of BWR Jet The EAP authorized development of IN at Chemical Pump Riser Elbow its 12/10/96 meeting.

Engineering  !

Branch i

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Page No. 9 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MifHLY STATUS REPORT Ceneric Comeunication and Compliance Activities Added.

Since the June 30, 1996 TAC Type Contact Tech Branch TR Comp Title Reason Added M97396 BL JWShapaker Reactor Systems --/--/-- BL 96-01, Sup 1, Control The EAP authorized development of BL Branch Rod Insertion Problems supplement at its 12/10/96 meeting.

M97397 IN JRTappert Electrical --/--/-- IN: Potential Deficiency The EAP authorized development of IN at Engineering of Electric Cable its 12/10/96 meeting.

Branch Connections M97436 IN DLSkeen Electrical --/--/-- IN: Potential Armature The EAP authorized development of IN at Engineering Binding in GE Type HGA its 12/17/96 meting.

Branch Relays 1

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Pagn No. 1 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Closed Since the Last Public Report (October 1996)

TAC Type Contact Tech Branch LA Comp Title R.eason Closed ,

M91599 GL JWShapaker' Reactor Systems 10/24/96 C GL 83-11 Supp: Licensee This GL Supplement was canceled per Branch Qualification For SRXB's request.

Performing Safety Analyses in Support of Licensing Actions  ;

M91620 GL JWShapaker Emergency 10/24/96 C GL: Revision to This proposed GL was canceled per Preparedness Augmentation Staffing PERB's request. (E-mail from TEssig to and Radiation Levels For Nuclear Power JShapaker 10/24/96).

Protection Plant Emergencies Branch i M93841 LT JMSebrosky Mechanical 10/29/96 C Implications of Target The EAP decided that no further GC ,

Engineering Rock 2-Stage SRV Pilot activitiy is needed at its 10/29/96 meeting. '

Branch Leakage M94841 IN ENFields Electrical 10/11/96 C IN: Loss of Offsite Power IN 95-04, Sup 1, issued 10/11/96.

Engineering and Reactor Trip with One Branch of Two EDGs Unavailable at Catawba Unit 2 M95686 IN RABenedict Events 11/26/96 C IN: Main Steam Safety IN 96-61 issued 11/20/96.

Assessment and Valve Failure to Reseat -

Generic Caused by an Improperly 1 Communications Installed Release Nut Branch j i

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t Paga No. 2 01/09/97 i PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Closed Since the Last Public Report (October 1996) .

TAC Type Contact Tech Branch LA Comp Title Reason Closed '

M96193 IN WFBurton Reactor Systems 10/31/96 C IN: RCP Seal Replacement IN 96-58 issued 10/30/96.

Branch with Pump On Backseat M96260 IN NKHunemuller Plant Systems 12/10/96 C IN: Modification to IN 96-64 issued 12/10/96. l Branch Containment Blowout .

Panels without l Appropriate Design  !

Controls M96289 IN ENFields Special 11/5/96 C IN 96-40, Sup 1, IN 96-40, Sup 1, issued 10/7/96.

Inspections Deficiencies in Material  :

Branch Dedication and  ;

Procurement Practices and  !

in Audits of Vendors L

t M96322 IN CDPetrone Instrumentation 10/28/96 C IN: Problems Associated IN 96-56 issued 10/22/96.  ;

with Testing or Tuning of and Controls Branch Digital Control Systems While at Power -

M96361 IN SSKoenick Reactor Systems 12/20/96 C IN:' Boron Dilution and IN 96-69 issued 12/20/96. -

Branch Other Activities i Affecting Reactivity M96400 IN CVHodge Containment 11/6/96 C IN: Revised Calculation No need for the IN because (nly small Systems and of High Energy Line Break number of plants are affected. The EAP i Severe Accident from Reactor Water agreed this assessment at its 11/5/96 Branch Cleanup Piping meeting. .

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Paga No. 3 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Closed Since the Last Public Report (October 1996)

TAC Type Contact Tech Branch LA Comp Title Reason Closed M96437 IN JRTappert Plant Systems 12/19/96 C Vulnerability of EDGs to IN 96-67 issued 12/19/96.

Branch Fuel Oil / Lubricating Oil Incompatibility M96535 IN DLSkeen Safeguards 12/27/96 C IN: Licensee Response to IN 96-71 issued 12/27/96.

Branch Indication of Tampering, Vandalism, or Malicious Mischief M96536 IN EJBenner Containment 10/28/96 C IN: Inadequate NPSH of IN 96-55 issued 10/22/96.

Systems and ECCS and Containment Heat Severe Accident Removal Pumps under Branch Design Basis Accident Conditions '

i M96694 IN EJBenner Reactor Systems 12/11/96 C IN: Undetected IN 96-65 issued 12/11/96. '

Branch Accumulation of Gas in RCS and Inaccurate Reactor Water Level Indication during Shutdown M96703 IN DLSkeen Electrical 11/26/96 C IN: Failure of RMS-9 IN 96-62 issued 11/20/96.

Engineering Overcurrent Trip Device Branch Programmers

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Paga No. 4 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Closed Since the Last Public Report (October 1996)

TAC Type Contact Tech Branch LA Comp Title Reason Clusad M96713 IN JRTappert Plant Systems 11/14/96 C IN: Potential for Water IN 96-60 issued 11/14/96. -

Branch Hammer in RHR Heat Exchanger M96748 IN DLSkeen Mechanical 12/19/96 C IN: Incorrect Effective IN 96-68 issued 12/19/96.  ;

Engineering Diaphragm Area Used to Branch Calculate the Bench Set of Safety-Related A0Vs M96766 IN TJCarter Containment 10/30/96 C IN: Potential Degradation IN 95-59 issued 10/30/96.

Systems and of Post LOCA Severe Accident Recirculation Capability Branch as a Result of Debris i M96969 IN JRTappert Emergency 11/6/96 C IN: Incident-Reporting IN 96-57 issued 10/30/96, all work done Preparedness Requirements Involving in the same week.

and Radiation Intakes, During a 24-Hrs Protection Period That May Cause a  ;

Branch TEDE in Excess of 0.05 Sv  ;

M97148 IN SSKoenick Information 12/24/96 C IN: Impact of Year 2000 IN 96-70 issued 12/24/96.

Management on Computer Software Branch

_ _ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,._ ____ ___ __,_______,m, . _ _ , . __ __ _ __ ______

Paga No. 1 'I I

01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance-Activities Closed  !

Since June 30, 1996 TAC Type Contact Tech Branch LA Comp Title Reason Closed M91447_ GL JWShapaker Reactor Systems 6/26/96 C GL: Boraflex Degradation GL 96-04 issued 6/26/%. i Branch in Spent Fuel Pool Storage Racks M91599 GL JWShapaker Reactor Systems 10/24/96 C GL 83-11 Supp: Licensee This GL Supplement was canceled per Branch Qualification For SRXB's request.  !

Performing Safety Analyses in Support of  ;

Licensing Actions r M91620 GL JWShapaker Emergency 10/24/96 C GL: Revision to This proposed GL was canceled per Preparedness Augmentation Staffing PERB's request. (E-mail from TEssig to ,

and Radiation Levels For Nuclear Power JShapaker 10/24/96).

Protection Plant Emergencies Branch ,

M92294 LT NKHunemuller Human Factors 7/1/96 C Develop Regulatory Guide This TAC closed per memo from COThomas Branch For Part 26 to Describe to AEChaffee, dated 7/1/96.

Acceptable Methods For i FFD Programs to Address Fatigue M93336 GL JWShapaker Operator 8/20/96 C GL: Exemption For TAC closed per memo from SARichards to Licensing Applicants For the Senior AEChaffee 8/14/96.

Branch Reactor Operator License Limited to Fuel Handling 1 (LSRO)

Paga No. 2 01/09/97 '

PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Closed i Since June 30, 1996 i TAC Type Contact Tech Branch LA Comp Title Reason Closed i M93643 IN EJBenner Materials and 6/5/96 C IN: Augmented Examination IN 96-32 issued 6/5/96.

Chemical of Reactor Vessel Engineering Branch i M33706 GL JWShapaker Mechanical 9/18/96 C GL: Periodic Verification GL 96-05 issued 9/18/96 Engineering of Design-Basis Branch Capability of Safety-Related Motor-Operated Valves M93707 GL JWShapaker Civil 9/3/96 C GL: Plant Shutdown TAC closed per ECGB's request (RRothman t Engineering and Criteria Following an e-mail to JWS 8/29/96)

Geosciences Earthquake Branch -

M93841 LT JMSebrosky Mechanical 10/29/96 C Implications of Target The EAP decided that no further GC Engineering Rock 2-Stage SRV Pilot activitiy is needed at its 10/29/96 Branch Leakage meeting.

M93979 IN JRTappert Special 9/16/96 C IN 92-68, Supp: IN 92-68, Sup 1, issued 9/16/96.

Inspec'tions Potentially Substandard Branch Slip-On, Welding Neck, and Blind Flanges M94615 IN JLBirmingham Analytical 7/5/96 C IN: Users of Decay Heat IN 96-39 issued 7/5/96.

Support Group Standard ANS 5.1 Get Different Results

t Page No. 3 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTNLY STATUS REPORT Generic Communication and Compliance Activities Closed Since June 30, 1996 TAC Type Contact Tech Branch LA Comp Title Reason Closed M94794 IN ENFields Special 7/25/96 C IN: Deficiencies in IN 96-40 issued 7/25/96.

Inspections Material Dedication and .

Branch Procurement Practices and '

Vendor Audits M94841 IN ENFields Electrical 10/11/96 C IN: Loss of Offsite Power IN 95-04, Sup 1, issued 10/11/96.

Engineering and Reactor Trip with One Branch of Two EDGs Unavailable at Catawba Unit 2 M95074 IN DLSkeen Special 9/4/96 C IN: Problems with IN 96-50 issued 9/4/96 Inspections Westinghouse DHP Circuit  ;

Breaker Levering-In Branch Device M95251 IN EJBenner Materials and 7/10/96 C IN96-09, Sup 1, Damage in IN 96-09, Sup 1, issued 7/10/96.

Chemical Foreign Steam Generator Engineering Internals Branch M95356 IN TAGreene Civil 9/20/96 C IN: Possible ANSYS Code Based on the 8/27/96 memo from GBagchi Engineering and Platform Dependency to AEChaffee, this TAC is closed. It Geosciences is not necessary to issue an IN Branch regarding the Holtec's erroneous analysis results using the ANSYS computer code.

i

Paga No. 4 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Closed Since June 30, 1996 TAC Type Contact Tech Branch LA Comp Title Reason Closed M95374 IN SSKoenick Reactor Systems 7/26/96 C IN: Overpower due to IN 96-41 issued 7/26/96.

Branch large Reduction in Feedwater Temperature M95684 IN TAGreene Mechanical 8/20/96 C IN IN 96-48 issued 8/21/96.

Engineering Motor-Operated Valve Branch Performance Issues M95685 IN TJCarter Instrumentation 8/5/96 C IN: Multiple Unexpected IN 96-42 issued 8/5/96.

and Controls Opening of Safety Relief Branch Valves M95686 IN RABenedict Events 11/26/96 C IN: Main Steam Safety IN 96-61 issued 11/20 36.

Assessment and Valve Failure to Reseat Generic Caused by an Improperly Communications Installed Release Nut Branch M95714 BL JWShapaker Events 7/5/96 C BL: Chemical, Galvanic, BL 96-04 issued 7/5/96.

Assessment and or Other Reactions in Generic Spent Fuel Storaga Casks Communications Branch M95720 IN DLSkeen Electrical 8/2/96 C IN: Failures of GE IN 96-43 issued 8/2/96.

Engineering Magne-Blast Circuit Branch Breakers

P ga No. 5 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Closed Since June 30, 1996 TAC Type Contact Tech Branch LA Comp Title Reason Closed M96075 IN EJBenner Electrical 8/5/96 C IN: Cracking of Phenolics IN 96-44 issued 8/5/96.

Engineering in Recator Trip Breakers Branch M96193 IN WFBurton Reactor Systems 10/31/96 C IN: RCP Seal Replacement IN 96-58 issued 10/30/96.

Branch with Pump On Backseat M96194 IN DLSkeen Electrical 8/13/96 C IN: Zinc Plating in GE IN 96-46 issued 8/12/96. '

Engineering Magne Blast Breakers Branch M96195 IN JRTappert Plant Systems 8/12/96 C IN: Post-Accident Failure IN 96-45 issued 8/12/96.

Branch of Containment Coolers M96259 IN TJCarter Containment 8/20/96 C IN: Thermally Induced IN 96-49 issued 8/20/96.

Systems and Overpressurization Severe Accident Branch M96260 IN NKHunemuller Plant Systems 12/10/96 C IN: Modification to IN 96-64 issued 12/10/96.

Branch Containment Blowout Panels without Appropriate Design Controls M96276 GL JWShapaker Plant Systems 9/27/96 C GL: Assurance of GL 96-06 issued 9/30/96 Branch Equipment Operability and Containment Integrity during Design Basis Accident

i Paga No. 6 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Closed Since June 30, 1996 TAC Type Cori t Tech Branch LA Comp Title Reason Closed i

M96289 IN ENFields Special 11/5/96 C IN 96-40, Sup 1, IN 96-40, Sup 1, issued 10/7/96.

• Inspections Deficiencies in Material Branch Dedication and  ;

Procurement Practices and in Audits of Vendors M96322 IN CDPetrone Instrumentation 10/28/96 C IN: Problems Associated IN 96-56 issued 10/22/96. ,

and Controls with Testing or Tuning of Branch Digital Control Systems While at Power M96323 JWShapaker Materials and 9/6/96 C GL: TS Revisions TAC closed per request from EMCB (Treed Chemical Supporting Implementation e-mail to JWShapaker 8/21/96). -

Engineering of 10 CFR 50.xx " Steam Guidance on the development of TS to ,

Branch Generator Tube Integrity comply with the "SG rule" will be r for Operating NPPs" included in the FR notice, therefore, ,

there is no need for a GL.

M96361 IN SSKoenick Reactor Systems 12/20/96 C IN: Boron Dilution and IN 96-69 issued 12/20/96.

Branch Other Activities Affecting Reactivity M96400 IN CVHodge Containment 11/6/96 C IN: Revised Calculation No need for the IN because only small Systems and of High Energy Line Break number of plants are affected. The EAP Severe Accident from Reactor Water agreed this assessment at its 11/5/96 Branch Cleanup Piping meeting.

i 1 -- - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - - - - _ _ - - - - - - _--!

Paga No. 7 01/09/97 PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Closed i Since June 30, 1996 TAC Type Contact Tech Branch LA Comp Title Reason Closed M96437 IN JRTappert Plant Systems 12/19/96 C Vulnerability of EDGs to IN 96-67 issued 12/19/96.  !

Branch Fuel Oil / Lubricating 011 Incompatibility M96535 IN DLSkeen Safeguards 12/27/96 C IN: Licensee Response to IN 96-71 issued 12/27/96.  !

Branch Indication of Tampering, ,

Vandalism, or Malicious Mischief  ;

10/28/96 C IN: Inadequate NPSH of I M96536 IN EJBenner Containment IN 96-55 issued 10/22/96.

Systems and ECCS and Containment Heat ,

Severe Accident Removal Pumps under r Branch Design Basis Accident l Conditions ,

M96694 IN EJBenner Reactor Systems 12/11/96 C IN: Undetected IN 96-65 issued 12/11/96.  !

Branch Accumulation of Gas in  ;

RCS and Inaccurate i Reactor Water Level -

Indication during i Shutdown M96703 IN DLSkeen Electrical 11/26/96 C IN: Failure of RMS-9 IN 96-62 issued 11/20/96.

Engineering Overcurrent Trip Device i Branch Programmers l l

I

Pcgm No. 8 '!

01/09/97 '

PUBLIC JANUARY 1997 DIRECTOR'S MONTHLY STATUS REPORT Generic Communication and Compliance Activities Closed Since June 30, 1996 TAC Type Contact Tech Branch .LA Comp Title Reason Closed M96713 IN JRTappert Plant Systems 11/14/96 C IN: Potential for Water IN 96-60 issued 11/14/96.

Branch Hammer in RHR Heat Exchanger M96748 IN DLSkeen Mechanical 12/19/96 C IN: Incorrect Effective IN 96-68 issued 12/19/96.

Engineering Diaphragm Area Used to Branch Calculate the Bench Set of Safety-Related-A0Vs M96766 IN TJCarter Containment 10/30/96 C IN: Potential Degradation IN 96-59 issued 10/30/96.

Systems and of Post LOCA Severe Accident Recirculation Capability Branch as a Result of Debris M96969 IN JRTappert Emergency 11/6/96 C IN: Incident-Reporting IN 96-57 issued 10/30/96, all work done Preparedness Requirements Involving in the same week.

and Radiation Intakes, During a 24-Hrs Protection Period That May Cause a Branch TEDE in Excess of 0.05 Sv M97148 IN SSKoenick Information 12/24/96 C IN: Impact of Year 2000 IN 96-70 issued 12/24/96.

Management on Computer Software Branch

! l l

DISTRIBUTION for NRR Director's Status Report

, CentralFile Public Document Room PGEB R/F l

~

FMiraglia AThadani BSheron RZimmerman TTMartin DMatthews FAkstulewicz EMcKenna PWen EWang Mr. William Rasin, Vice President '

Technical / Regulatory Division ,

Nuclear Energy Institute 4

1776 " Eye" Street ,

l Washington, D.C. 20006 , ,

Mr. R. P. LaRhette  !

Institute of Nuclear Power Operations ,

1 700 Galleria Parkway '

Atlanta, Georgia 30339-5979 .. ,

Mr. Lee Watkins J Assistant Manager For High Level Waste U.S. DOE 4 PO Box: A -

Aiken, South Carolina 29892

Mr. R. W. Barber Safety and Quality Assurance, DOE -

270 Corporate Center (E-853) 20300 Century Blvd.

3 Germantown, MD 20874 Mr. S. Scott

Office of Nuclear Safety, DOE

Century 21 Building (E-H72) i 19901 Germantown Road Germantown, MD 20874-1290 Mr. Bob Borsum 1700 Rockville Pike, Suite 525 0f Rockville, MD 20852 # l 0J ,

Ms. Norena G. Robinson Licensing Technician Q Nebraska Public Power District Cooper Nuclear Station p#/W g

/ltf g P. O. Box 98 Brownsville, NE 68321 . i l

pu*

' ..L I,

OFFICE PGES:DRPMs PGEB:DRPM j PGEB:DRPM SC/M8tD$tPM C/PM :bRPM @ FW M gg NAME EWang r L~ PWen WW EMcKennat, FAktfulewicz DMadhews TTMArtin DATE 01p/97 Othp? 01M/97 01tgd97 01 @ 7 01 @ 7 , Q-h (JM:

8 0FFICIAL RECORD COPY ,gj g e.

NRC FILE CENTER COPY g%

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