ML20141J697

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Addresses Requirement That NRC Ensure Formal Tracking & Follow Up on Issues Re Facility Event,Per 900608 Commission Briefing by NRC on Results of Facility Incident Investigation.Plans & Schedule for Resolution of Items Encl
ML20141J697
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 08/08/1990
From: Taylor J
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To: Carr
NRC COMMISSION (OCM)
Shared Package
ML20141J689 List:
References
FOIA-91-468 NUDOCS 9008100100
Download: ML20141J697 (11)
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AUG 0 81990 l 5 [

MEMORANDUM FOR: Chairman Carr Commissioner Rogers /

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Commissioner Curtiss i Commissioner Remick FROM:

- James M. Taylor Executive Director for Operations

SUBJECT:

STAFF ACTIONS RESULTING FROM THE V0GTLE UNIT 1 INCIDENT INVESTIGATION

p the June 8,1990, the Commission was provided a briefing by the NRC staff on the results of the Vogtle incident investigation. The Staff Requirements -

Memorandum, dated June 28, 1990, documented the staff requirements which evolved from the briefing. The purpose of this memorandum is to address the N* ~ requirement that the staff ensure formal tracking and follow.up on issues relating to.the Vogtle event, including the follow-up action plans and the schedules-for completion of each item.

Manual Chapter 0513, NRC Incident Investigation Program, sets forth the requirementsforfollow.upactionsonIncidentInvestigationTeam(IIT) findings. . Pursuant. to MC-0513, I assigned staff actions in a memorandum dated June 21,'1990, to follow-up on the findings documented in the Vogtle llT report. Each of_the assigned offices / region was requested to pro,ide a written summary of the plans, schedule, status and point of-contact for each item within their area of. responsibility. The enclosure to this memorandum provides a compilation of the action plans and completion schedules developed

.by the responsible offices / region for each assigned follow-up action item.

Resolution of the assigned plant-specific actions will be documented-in a single report and each generic action will be individually tracked via the E00's work item tracking system-(WITS). Overall lead responsibiHty for -

preparation of the staff's single report on plant. specific actions rests.with eg Re ion 11. The Office of Analysis and Evaluation of Operational Data (AE00) wi 1 track and periodically document the status of each item in the AE00- [Mg#g-Annu.1 Report through final resolution or disposition. AE00 will also prepare a closecut report- which will identify the resolution or disposition of all of

'the Ili findings and conclusions. Original Sigra ..

J mE k ihlor Executive Director for Operations

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I ENCLOSURE

. PLANS.AND:$CHEDULE FOR RESOLtITION OF '

V0GTLE IIT--STAFF ACTION ITEMS

1. - _ ISSUE: Adequacy of Shutdown-Risk Management
ACTION:

-- l a'. . Review h .. Jv 'latory guidance related to' shutdown risk control and

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e ice as may be needed. _ Include-in-the assessment of .i shu' a r'-

ment: normal and standby electrical systems :and isour<. - - wltchyard- equipment; ~. normal and alternate cooling syste . .

trnate plans for loss of forced circulation;. fission produ. . < ;luding primary and containment systems and: special activb xovement of heavy loads or construction activities.

RESPONSIBLE _ OFFICE:

NRRj(RES-suppor_tasneeded)-

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ACTION PLAN
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NRR -(Reactor Systems Branch) has_ begun assessing NUREG-1410 findings in order to establish; specific tasks and milestones. Those specific tasks-

-will be integrated into the overall NRC action plan for addressing risks
during; shutdown'.. .

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Completion by19/91.

' ACTION:.

lb. ' 1 Continue !to develop - shutdown risk analysis methodology :and review the '

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' effectiveness of alternate cooling methods for loss of forced circulation.

e Issue new guidance as; appropriate.

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RESPONSIBLE OFFICE:

2 RES~-

4 ACTION PLAN:

,'  : Shutdown Risk Analysis Methods

-- RES will continue to develop risk methods _ for .non-full power operating.

' modes, including'the shutdown mode. Demonstration application of these

' methods will be performed for two plants: - Surry and Grand Gulf. The set J Lof _initia. ting events to be considered include those internal events 2

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s normally considered in risk analyses (e.g., pipe ruptures) as well as even'.s special to low power and shutdown conditions. Screening Fires and floods initiated within the plant are included in the set. analyses will be performed first to rank plant events according to importance to core damage frequency and risk. A detailed study of the most important events will- then be performed. This work is -being performed in coordination with NRR's plan for shutdown risk management analysis.

Effectiveness of Alternate Cooling Methods NUREG-1410 proposes two alternate methods for continued core cooling, after Loss of RHR during mid loop operations. The first method is to use gravity feed of water from the refueling water storage tank into the reactor vessel. The staf f has determined that research is not required to confirm this method, as long- as a continuous flow can be assured. The other method, reflux cooling in the presence of non-condensible gases, is a cooling mode that has not been studied extensively and is not completely understood. Research planning efforts will be concentrated in this method.

The staff is currently collecting and evaluating experimental and analytical data applicable to the thermal-hydraulic processes-involved in loss of RHR during mid-loop operation. These data are being studied to evaluate (a) the potential plant conditions which may result and the cooling methods which may exist; (b) the controlling thermal-hydraulic phenomena' associated with these conditions as well as a determination of data; and (c) the conditions and phenomena requiring relevant additional researc to provide a valid basis for regulatory actions.

existing h SCHEDULE:

- Shutdon Risk Analysis Methods Complete _ screening analyses _ and develop perspectives (NRR support) by 5/91 Complete detailed risk analysis of most important event by 3/92 Complete analysis of other important events.by 12/92 Effectiveness of Alternate Cooling Methods, Completion by 6/91 ACTION:

Ic. Review the present regulatory requirements such as standard technical specifications for shutdown conditions and revise as needed, bawd on the results for Action la above. Develop guidance regarding revision of documents such as E0Ps, accident management procedures and plant technical specifications as necessary.

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HRR ACT10N PL ANS:

NRR (Technical Specification Branch) has begun assessing the applicable NUREG-1410 findings and anticipates that completion of this action will involve numerous meetings with industry Owners Groups. Specific milestones and tasks have not -yet been developed. Once the specific tasks are established, they will be integrated into the overall NRC Action Plan for Addressing Risks During Shutdown.

SCHEDULE:

Completion by 9/91 4

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2. ISSUE: Adequacy of Control Over Switchyard Activities ACTION:

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2a. Evaluate the adequacy of existing regulatory guidance and requirements for .

the control of activities and - hazardous materials in switchyards and protected areas. Issue new guidance as necessary.

ELSPONSIBLE OFFICJ:

HRR(RESSupportasneeded)

ACTION PLAN:

NRR (Haterials and Chemical Engineering Branch) is currently reviewing the applicable NUREG 1410 findings. Specific milestones and tas':s have not yet been developed; however, consideration is being given to an Infonnation Notice.

52EDULE:

Completion by 12/90 ACTION:

2b. Evaluate the corrective actions taken at Vogtle to ensure adequte control of activities and ha?ardous materials in the switchyard.

RESPONSIBLE OFFite 9.g

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ACTION PLAN:-

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Region II will review: (1) the imediate corrective actions of the licensee for access control to the Unit I switchyard (Reactor- Projects

' Section); (2) site security and safety procedures.: to . ensure adequate guidanc2 exists for vehicular movement control (Reactor Projects Section),

Resident Inspector and Safeguards Section); (3) '.he . site administrative procedures concerning spotting of portable equipment and ' topping off pra;tices of portable-equipment (Reactor Projects and Resident Inspector) and; will inspect; (4):the application of the guidance provided in (1) through (3). above-(Reactor Projects Section and Resident laspector); and (5) the General ' Employee Training . program to ensure incorporation of vehicular movement control guidance into the safety training portion of

' the program (Reacter Projects, Resident Inspector and Operational Progr;ms Section).

SCHEDULE:

Complete (1) by 4/S0 5

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Complete l(2) by 9/90-Complete-(3)by 9/90 Complete (4) by 11/90 Complete (5)by-12/90 Adequacy of- Diesel Generator Instrumentation and ' .ol .

3. ISSUE:

Systems

' ACTION:

3a. - Evaluate 'the' need for reexamination of emergency- diesel generator annunciators and control panels including provisions for alarm printout.

Consider the need for reexamination of local sequencer panels.

BESPONSIBLE OFFICE:

NRR KIldNEAj:-

NRR (Electrical Systems Branch) is reviewing the applicable NUREG-1410 findings in order to establish specific milestones and tasks.

SCHEDt&f:

Completion by-12/90 E1198:

3b. Evaluate Ithe- need for . additional- guidance and increased emphasis on procedures and traintag for emergency diesel and local sequencers-including

- response to malfunctions.

RESPONSIBLE 0FFISf

NRR AC. TION PLAN:

NRR (Electrical Systems Branch) is reviewing the applicable NUREG-1410

' findings.in order to establish specific milestones 'and tasks.

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Completion by 12/90 l

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?and7 1ocal: sequencer panel > operations including response to malfunctions. .;

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RegionLI! will::-(l) review the licensee's actinns for operational feedback

" toiensure:the EDG and --sequencer, start'and: restart features and guidance ,

concerning? logging _m.alfunctions have been disseminated to all operators l-(Reactor Projects Section,' Resident Inspector); (2) review the licensee's L" surveillance instructions to ensure design changes and calibration " lessons -

3e llearned" haveLbeen incorporated (Plant Systems) Section);' (3) verisy .

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ioperators proficiencyEinLEDGEando localisequencer operations via Job-s L . JPerformance Measures duringl annual' requalification examinations '(Operator i

, Licensing Section);'and-(4) conduct a performance based training inspection Lt - Eusingithet MarchT20, 1990i eventJas7the entry point.

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4. ISSUE:- Adequacy of Emergency Preparedness

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ACTION:-

-4a. Evaluate and revise, as necessary. the: guidance contained in N" REG 0654 i to classify events that could occur =in ccid shutdown and loss of electrical power events. Evaluate the NRC guidance to licensees on classification procedures and revise as appropriate. Evaluate the guidance Revise and- to licensees follow up as.

-for personnel accountability during outages.

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. appropriate. Evaluate guidance-to licensees regarding the' availability of-notification systems (and alternates) during a loss of power event- ,

Consider' the-priorities and requirements for notifications to off-site authorities. _ Follow up_-as appropriate.- ,

RESPONSIBLE _QFflCE:

NRR-(AE00 support.as needed)

AGJ10_N PLAN:-

NRR (the Emergency Preparedness Branch) is reviewing the applicable NUREG-1410 findings to establish specific milestones and tasks. This effort is

being' integrated 11nto the overall NRC action plan for Addressing Risks During Shutdown, SCHEDULE:

Completion 9/91 ACTION:-

-4b. Evaluate the policy and guidance to NRC managers for determining when the

?NRC ? will . enter the standby--mode. Initiate _ follow-up . actions,- as_

' appropriate.

Identify and correct Vogtle's recent ENS problem., .

.RESPONSIBLLQFLL(1:-_

AE00' h JCTION PLAN:

AE00 is currently reviewing'the procedures for headquarters andLregional management- to determine whether they are sufficiently clear and concise-- '

l K in establishing criteria for. the Agency entry into the standby mode. Upon completing the review, procedures will be ' modified, if appropriate.

Actions will: be communicated to headquarters and regional management to include training and additional exercises when warranted.

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AE00 (Incident Response Branch) has requested IRH's assistance in determining the cause of the communications problems during tha Yogtle event. The action has been completed.

$Q[(QUE:

AE00 Completion by 10/90

5. ISSUE: Adequacy of Operating Experience Feedback ACll08:

Sa. Evaluate the procedures and practices for events analysis and feedback of lessons to industry and recommend appropriate improvements. Consideration should be given to: (a) past NRC reports not the subject of " generic communications," and (b) the development of the proper t: ope of the generic actien based on the individual events. Also, address the need for feedback vegarding the Calcon sensor failures and calibration issues arising from the Vogtle event.

B11tDNSIBLE OFFICE:

NRR bCTION PLAN:

NRR-(Generic Communications Branch) is reviewing the applicable NURf 3-1410 findings to establish the specific milestones and tasks. The

-Instrumentation and Controls Branch has prepared an Information Notice which is near issuance regarding Calcon sensor failures.

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SCHEDULE: ~

Completion by 6/91 4110H:

5b. Review . th'e industry's NPRDS program regarding: (1) the need for improvements in ' reporting guidance or practices for diesel- generator components, and (2) industry practice in providing NPRDS reported component failures to vendors or the level of vendor use of NPROS. Interface with INPO as appropriate for action on this and the staff's overall evaluation of NPRDS to _ stimulate improvements.

ELSPONSIBLE OFFICE:

AE00 ACTION PLAN:

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The discussions on item:(1) will focus on the ' adequacy of the NPRDS reporting guidance for engineering records and failure reporting. .The discussions on item (2) will focus- on the availability of the NPRDS information to vendors. Recommendations for further industry actions, if any, will be communicated to industry through the appropriate channel (e.g., correspondence, NPR05 Users Group sctivities, information notice).

AE00 will also discuss 'with INPO the staff's overall evaluation of NPh05 in order.to stimulate improvements.

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Completion-by 12/90

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