ML20202J093

Insp Rept,South Reactor Feedwater Pump Turbine Failure. Contract Number Illegible.Related Info Encl

ML20202J093
Person / Time
Site:	Fermi
Issue date:	02/28/1986
From:	Meils E NUCLEAR ENGINEERS & CONSULTANTS, INC.
To:	NRC
Shared Package
ML20202H992	List: ML20202H989 ML20202H996 ML20202J004 ML20202J012 ML20202J016 ML20202J021 ML20202J031 ML20202J052 ML20202J080 ML20202J093 ML20202J125 ML20202J156 ML20202J187 ML20202J204 ML20202J231 ML20202J262
References
FOIA-86-244 NUDOCS 8607170023
Download: ML20202J093 (47)

Text

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( EUEi-i) ,

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J *. e A8.anda Visit of E. Adenaam and M. Lvneh Monday - February 10. 1986 9

30 Arrival 9:30 Resident Inspector Briefing 206 NOC Paul Byron Mike Parker Walt Rogers 10:30 Edison Presentation 352 NOC See attached Agenda 12:30 Lunch NOC 1:30 Plant Tour OBA Bob Lenart Rob Woolley NRC v

Tuesday - Feb ruary 11. 1986 c' -T

-9 00' Training Tour 214 NOC Jim Coleman

- Simulator (heat up) Rob Woolley

- Classroom (tech specs) 262B NOC tea I n .nn - EOF 164 NOC Tom Randazzo

- ERIS Demonstration Ed Griffing

- 50.54(f) Response Rob Woolley 11:00 Design Issues 352 NOC Syl Noetzel George Trahey Frank Agosti Ed Griffing Tom Randazzo Rob Woolley 12:00 Lunch / Exit Discussion NOC 2:15 Flight to Washington

k DETROIT EDISON PRESENTATIONS TO E. ADENEAM/M. LYNCH l

TOPIC PRESENT0R 10:30 Introduction F. Agosti Fermi 2 Organization F. Agosti 10:45 Plant Status and Milestones R. Lenart through 100% Power 11:30 Licensing Status R. Woolley

. Restart Licensing Issues

. License Conditions / Commitments 11:45 Open Discussion F. Agosti Noon Plant Tour Preparation R. Lenart Attendees: Frank Agosti. Ed Griffing, Bob Lenart, Syl Noetzel, Jim Piana, Tom Randazzo, George Trahey, Rob Woolley, Al Wegele, Joe Conen, Lew Bregni

( .,

f S & W EVALUATION Directed by C. M. HEIDEL (President, DECO)

PURPOSE:

o ASSESS ENGINEERING PROCESSES TO DETERMINE IF EEINEERING WORK PACKAGES AND ASSOCIATED CHANGES WERE/ARE IDENTIFIED, PRIORITIZED A*ID CONTRCLLED IN A MANNER TO SUPPORT FUEI. LOAD AND RESTART.

o PERF0PN EVALUATION OF DESIGN CONTRCL PROCEDURES TO ASSURE THAT PROPER CONTROL OF THE DESIGN PROCESS IS MAINTAINED.

{Ref. 50.54(f).)

SCOPE:

o TRANSITION PROJECT EEINEERIE - NUCLEAR EEINEERIE.

(ca 3rd Qtr. '84) to now.

o EVALUATE PROCESSES & THEIR IMPLEMENTATION.

EVALUATION TEAM -

o EXPERIENCED ENGINEERS FROM S&W - BOSTON.

I o APPROPRIATE DISCIPLINES REPRESENTIE CROSS-SECTION OF BACKGROUNDS IN NUCLEAR POWER PLANT DESIGN, COMPLETION, OPERATION & EVALUATION ACTIVITIES.

! STAIUS -

o MOBILIZED 2/10/86, o PLAN APPROVED 2/11/86.

o ORIENTATION INITIATED.

}

o IMPLEMENTATION OF PLAN 2/12/86, i

I i

v. , . is ......., ,.

CntlLC % Att O id Q,f

g. -

VICE PRE $10E~.1 '

• Ig M N ' ,

RUCLEAR OPERATien$ ',

MANAGER huCLEAR OPERATIONS (v.w.t.1)  ?

I I I I AS$$$ TANT MANAGER A$53$1 Ant mAmAGER GENERAL DIRECTOR 111!$iAIT MANAGER huCIEAR OPERAll0NS

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DETROIT EDISON PRESENTATIONS TO E. ADENSAM/M. LYNCE 1

TOPIC PRESENT0R 4

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10:30 Introduction F. Agosti j Fermi 2 Organization F. Agosti 10:45 Plant Status and Milestones R. Lenart

through 100% Power

. 11:30 Licensing Status R. Woolley 1

. Restart Licensing Issues

. License Conditions / Commitments

) 11:45 Open Discussion F. Agosti

Noon Plant Tour Preparation R. Lenart 1

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STATUS OF LICENSE CONDITIONS AND MAJOR COMMITMENTS 1

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SUPPRESSION POOL TEMPERATURE MEASUREMENTS (2.C.(5) i

! IMPLEMENT SYMPTOMATIC E0Ps REY 4 (ATT 2, 3.(b))

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'i SRM COUNT RATE SUBMITTED 12/23/85 FEDERAL REGISTER NOTICE 01/29/86 COMMENT PERIOD END 02/28/86 1

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EARTHQUAIT OF JANUARY 31, 1986  !

DESIGN ISSUES:

o SEISMIC o EQUIPE!E QUALIFICATION o DESIGN VERIFICATION OF CHANGE DOCUME!ES DER-85-712 o EMBEDDED PULTES o HANGER LOG BON o CONCLUSION e

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Eartheumlee of Janua-v 11. 1986 1, Femi 2 seisnic nonitoring system

. Active sensors with a seismic trig 6er preset at an acceleration of .01g.

. Six passive peak shock recorders.

2. Response of Fermi 2 seimic monitoring system on January 31, 1986

. The active recorders did not actuate as a result of the earthquake. The active sei m ic recording system was functionally tested on February 1,1986, and detemined to be functional.

. The record plates of the passive peak shock recorders have been interpreted. The equivalent static acceleration of the recording device at the base mat at a frequency of 25.4 hertz was less than .01g. ~

3 Femi 2 design accelerations

. Operating basis earthquake (OBE)

Zero period acceleration (ZPA) a = .08g horizontal

. Safe shut down earthquake (SSE)

Zero period acceleration (IPA) a = .15g horizontal .

4. Effect of January 31, 1986 earthquaice on Perry Nuclear Plant in Perry, Ohio Fermi 2 engineers have had several telephone conversations with personnel of Cleveland Electric. On February 7, 1986,

, the Fermi 2 seismic _systens engineer and the seismic consulting engineer for Fenni 2 visited the Perry Plant and obtained the following unerrief ni information.

. The earthquake epicenter is located about 10 miles south of the Perry Plant.

. The USGS rated the earthquake at 4.9 on the Richter' scale.

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. Peak accelerations measured at Perry base mt elevation:

a = 0.45g W at 12 hertz (0.226 expected) a = 1.0g NS at 20 hertz (0.18s expected) 4 a = 0.7g vertical at.12 hertz zero period acceleration (ZPA) = 0.18g horizontal

. The event lasted 7 seconds.

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. Cleveland Electric will subciit a written seismic report to the NRC on 2/11/86.

. Thorough walkdowns of the plant have been performed. No damage to safety related stmetures or systems has been detected. Non-safety stmetures have experienced minor damage such as cracked. plaster, ceiling tile displacement.

. Cleveland Electric have operated all safety systens ready for operation since the earthquake.

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. .. l Sei mic Issue Prom er' W 1 .

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. Numerous EDPs and ECRs were generated by Nuclear Engineering from August 1984 thru August 1985 without evidence of seimic qualification review. (See DER NO-85-680) h&m &. r C pd

. Problec: was detected as a result of a survey of 50 EDPs and ECRs by Resident Engineering Arch / Civil in July 1985. This was a . j, SAFETEAM issue also. g f *r n ,

. Problem was doctnented via Engineering Asstrance audit finding t.* ![

A-QS-P-85-28-14 July 25, 1985.

Resciution

. Giffels Associates (GAI) was contracted to review 1995 change documents processed between Augpst 1984 and Auspst 1985.

. GAI classified the change doctnents as either type I (1000 seimic I or II/I) or type II (995 non-seimic).

. Identify type I change doctz:ent which already had been seismicly reviewed or= did not need a seimic review per procedure NE 3.9.(300 documents)

. Identify type I change doctments requiring fbrther investigation for seimic qualification. (54 documents)

. Detailed review of the 54 doctments requiring fbrther investigation revealed that all of the change documents are seismicly qualified and no hart! ware changes are rieeded.

. The GAI review was completed by 12/4/85. The Edison prepared SORS were cocpleted by -12/17/85.

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! . The cause of problem was lack of documentation adequcte to dec:onstrate seimic reviews had been coc:pleted in all cases throughout the period of developaent of Nuclear Engineering.

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_ _ . _ _ _ _ _ _ _ ..~___._m__.. .._ .. .~ . . .

EO REVIDI OF EI)Ps Statemnt of' Problem o Concern regarding seismic review of GP not having taken place. Outgrowth of sei mic concern. -

l Cause o Nuclear Engineering did not have an Equipment Qualification Group until November,1985.

o All EQ reviews were performed by Femi 2 Engineering in Troy.

o Needed to be sure all EDPs generated by Nuclear Engineering which required EQ review had been properly reviewed.

Solution to Problem

+ o Review initiated by NE-EQ group on November 25, 1985.

o 273 EDPs total, issued against 21 safety-related systems that contain EQ equipment was reviewed and completed on December 10, 1985.

o Results:

48 EDPs and related ECRs received EQ review.

53 contain equipment that either is located in mild enviroment or not required to operate in an accident environment.

106 non safety-related 20 cancelled 45 not yet issued 1 combined with another EDP that was in mild environment.

273 -

Cer.clusions:

o EDPs were properly reviewed and approved by QE group or properly determined that it is not applicable to EQ program.

o Nuclear Engineering, as of November,1985, is staffed with EQ group. As design modifications occur or existing equiprnent

• l becomes obsolete, new EQ equipment will continue to be l evaluated adequately.

r_ . . . .. . . . .. . ......s........ ~.. . . . .. .. . . . . . . . ..

DESIGN VERIFICATION OF NUCLEAR ElGINEERI!G GENERATG DE3IGN CHAf17 DOCUliEfn3 State-ent of Problg g..

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4 4 ' ~5, As a result of QSFs and audit findings, DER NO-85-712 issued on December 11, 1985 by Nuclear Engineering Department identified a potential generic problem regarding inadequate doctrientation of design review and verification of Nuclear Engineering generated safety-related design change doctrients (EDPs, ECRs, and ABNs). This was done at

. Edison initiative. 4, /;ur ,s c.i.

.Cauftt Procedure NE-2.5.7 Design Verification Rev. O issued 5-23-83, applied to all design documents generated or revised by NE or NP but did not require documentation of complete verification. J \ p as r%d *,

Solution to Problem g,ja., y ; . w. t. g DER Task Force formed to reverify design change paper.

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f *ethodolo nr l aster checklist and instructions developed (PCN No. 2 of NE-2.5.7) -

o- More than 60 attributes, including QA level, seisr.ic, environmental qualification, codes / standards, ccrmlitments/

requirements, piping / hanger stress, rattlespace, fire protection, alara, inspection requirements....etc.

o Supported by other checklists on specific items such as enviromental qualification, fire protection,1senetric, conduit...etc.

o Auditable record will be filed in Doctraent Control.

Status Schedule -

- February 20, 1986 expected completion Prorress -

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- Scope identified: approx. 111 EDPs, 250 ECRs and 250 ABNs.

- There are approximately 100 ite=s that emerged from the evaluation which need disposition.. All EDPs, ECRs and ABNs have been evalteted. These should be dispositioned prior to 2-20-86.

- No hardware changes have been identified to date.

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DESIGff CALCULATIOf,'S FOR Ef4PEDDED PLATES Statenent of Problem and Enckground During the process of performing the Reactor-Auxiliary Building design verification, calculations were prepared for stmetural embedded plates which had pipe supports, elect supports, etc., attached. During process of review, concem devcloped that scrne plates may be overloaded. Concern was reported to the NRC and systens affected taken .

out of service.

Issues

1. Why calculations not made sooner:

o Design process was to install embeddments - 1771.

o Design information on loads not available till end of piping analysis.

o Sec:e checks made to' determine embeddments okay.

o Decided to perform verification at time of building structure final verification.

2. During NRC audit errors found in some calculations.

3. One (1) calculation had not been verified before returning systems to service.

Cause of the Problem The cause of the problem was:

1. Failure of the engineer to recognize the difference between the documentation required for a technical answer to this problem and.the doctanentaton required to return the systec:s to service. ~

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2. Calculations not ntraerically checked.

3 Verification step not couplete.

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DESIC'i CS,.C.UM7 IONS FUR EMBEDDED PLATES Cont'd Solution of the Problem Engineering nust become more sensitive to the requirenents of an operating plant in that the design basis calculations uust be complete (both from the standpcint of verified and approved and from the standpoint of properly addressing all the appropriate design requirements) prior to returning a systen to service.

Numeric checks of calculations will be required.

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i Calculations have been completed and the embedded plates reviewed were qualified within code allowable stresses without modification.

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RECONCILIATION OF STRESS. REPORTS AND HAf5EF DESIGN CALCUU. TION HAPEER LDG Statement cf Problem Troy Engineering transmitted a listing of chan6e paper to Nuclear Engineering which included large bore stress reports, large bore piping hanger DCRs and small bore piping and tubing work of a similar nature. I i

Procram in Effect The program in effect was to bring up to date all QAI Class I stress reports as of 9-1-85. This was performed. The QAI Class I stress reports also had been revised and issued for fuel load incorporating all changes. The change paper was reviewed for impact en the stress reports, stamped accordingly and entered into the punchlist.

Change paper written against large bore pipe hanger sketches would be evaluated for impact against their design calculations. A reconciliation form would be filled out. It .

was to be signed by the preparer and a second engineer who is the verifier.

A DER was written to doctnent the fact that there was open change paper against stress reports and original hanger design calculations.

a Gaunt Stress Report - Computer Runs - Big effort to update.

This has been done periodically on Class 1 stress reports and others based on judgement of engineer. To keep track of changes, they were 1

logged.

Selution to Preblem -

Nuclear Engineering needs to be sure that design calculations are adequate, checked and verified to support operating plant. Therefore, the actions taken are:

permare calculation list to embedded plate list.

17 calculations used for embedded study are now listed on DER HO-86-006.

1 REC 0frTLTATIOf! OF STRESS REPO M Cont'd .

- Identify list of plant systems affected. -

o NSS has declared systems listed on DER-86-006 inoperable.

i;.v.a- %gr bp~w o Prioritize systen for clearing inoperable status.

f.'uclear Production priorities issued 2-3-86.

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- Review individual systems, ISOS & Hanger Sketches to be certain all changes are identified.

- Resolve problems, if any, and update or revise calculations if and as required.

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- Verify calculations and issue to Infonnation Systems.

Schedule Will be trying to complete by 2-28-86.

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I CO?CLUSION l

Threading through these examples is lack of documentation in some cases of the verification process.

Action Taken i Recently issued totally rewritten procedure requiring that: 8 i

1. Design nust have verification before release using checklists.

2. Engineering decisions will have to be doctsnented and verified.

This we believe will resolve our identified Root Cause problem.

In addition, an evaluation of Engineering by outside Edison third ;mrty is just getting started to be sure that:

1. We are ready for restart.

2. Our procedures and programs are adequate.

3 Needed improvements will be identified. ,

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