ML20212B488

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Summarizes 970924 Engineering Mgt Meeting Re Design Basis Efforts,Engineering Performance Indicators & Engineering Assurance Groups.Handouts Provided During Meeting Encl
ML20212B488
Person / Time
Site: Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle  Constellation icon.png
Issue date: 10/22/1997
From: Grobe J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Hosmer J
COMMONWEALTH EDISON CO.
References
NUDOCS 9710280097
Download: ML20212B488 (47)
v • d • e


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October 22, 1997 Mr. J. B. Hosmer Engineering Vice President Commonwealth Edison Company Executive Towers West 111 1400 Opus Place - Suite 900 Downers Grove, IL 60515

SUBJECT:

ENGINEERING MANAGEMENT MEETING

SUMMARY

Dear Mr. Hosmer:

On September 24,1997, we met with you and members of your staff to discuss e.ngineering activities at Comed. Specifically, the meeting discussion focused on design basis efforts, engineering performance indicators, and engineering assurance groups. This meeting was open to public observation. The handouts you provided to us during the meeting to aid in the discussion are attached. Wo jointly agreed to conduct another engineering management meeting in about 2 months (mid November) from this past meeting, in accordance with 10 CFR 2.790 of the Cor mission's regulations, a copy of this letter and the enclosure will be placed in the NRC Public Document Room.

Sincerely, Original Signed by John A. Grobe John A. Grobe, Director Division of Reactor Safety Docket No. 50-456; 50-457 Docket No. 50-454; 50-455 Docket No. 50-237; 50-249 -

Docket No, 50-373; 50-374' Docket No. 50-254; 50-265 Docket No. 50-295; 50-304 Enclosouro: As stated g Bi5',

See Attached Distribution DOCUMENT NAME: G: COMED.LTR v...

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October 22,1997 -

cc w/ encl:

_R. Ryback, Senior _BWR Nuclear Licensing Administrator

-T. Tulon, Site Vice President

- K. Graesser, Site Vice President J. S. Perry, Site Vice President W, T. Subalusky, Jr., Site Vice Prosident L. W. Pearce, Site Vice President J. Brons, Site Vice President-R. J. Manning, Executive Vice President, Generation M. Wallace, Senior Vice Ptwident, Corporate Services H. G. Stanley, Vice President, PWR Operabons Liaison Officer, NOC-BOD D. A. Sager, Vice President, Ger eration Support E. Kraft, Vice President, BWR Operations D. Farrar, Nuclear Regulatory Services Manager

1. Johnson, Licensing Operations Manager Document Control Desk - Licensing Braidwood Station Manager K. Kofron, Station Manager T. Nauman, Station Manager, Unit 1 M. Heffley, Station Manager, Units 2 and 3 Quad Cities Station Manager R. Starkey, Plant General Manager F. Dacimo, Plant General Manager T. Simpkin, Regulatory Assurance Supervisor D. Brindle, Regulatory Assurance Supervisor F, Spangenberg, Regulatory Assurance Manager P. Barnes, Regulatory Assurance Supervisor C. C. Peterson, Regulatory Affairs Manager R. Godley, Regulatory Assurance Supervisor Richard Hubbard

- Nathan Schloss, Economist, Office of the Attorney General State Liaison Officer Chairman, Illinois Commerce Commission State Liaison Officer, Wisconsin Mayor, City of Zion J. R. Bull, Vice President General & Transmission, MidAmerican Energy Company Distribution:

Docket File w/enci LPM, NRR - Braidwood, SRI, Braidwood, Byron,

. PUBLIC IE-01 w/ encl Byron, Dresden, LaSalle, Dresden, LaSalle, OCFO/LFARB w/enci Quad Cities, Zion w/enci Quad Cities Zion w/enci DRP w/enci J.- L. Caldwell, Rill w/enct A. B. Beach, Rlil w/enci DRS w/enci -

Rill Enf. Coordinator w/enci C. D. Pederson, Rlli w/enci Rlli PRR w/enct R. A. Capra, NRR w!enci G. E. Grant, Rlll w/enct TSS w/ enc!

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Comed l

Design Basis Initiative and l

Engineering Performance Update NRC Region III Offices September 24,1997 1

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+ Introduction Hosmer

+ Design Basis Initiative Egan

- status

- Results i

+ Engineering Management Measurements Renuart / Freeman

- Metrics

- Engineering Assurance Group

- Station Engineering Management 1

+ Closing Remarks Hosmer

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2 Design Basis Initiative Proj. ect i

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Dennis Egan NRCMeeting 9/24/97 3

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Project Goals i

+ Consistency between:

- UFSAR

- PlantTechnicalSpecifications

- Design Basis Document Manuals

- Design Basis Calculations and Analysis

- Plant Procedures l

- Physical Plant

+ Ownership and understanding of the Plant Design Bases by Comed Personnel 1

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+ Confidence that the Facility is being Operated within its l

Design Basis

+ Reduction in Time Needed to Research Key Plant Parameters

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NRCMeeting 9/24/97 4

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Design Information Relationships Procedures UFSAR calculations l

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Project Milestones r

i Activity Date Pilot at Zion 3/17/97 Issued Project Plan 3/28/97 i

Second Pilot 4/3/97 Round Table at Braidwood 4/18/97 Issued DBI NEP 5/23/97 l

Initiate Training of DBI Personnel 5/27/97 DBdb Operational 6/5/97 i

LaSalle Effort Postponed 6/27/97 First Self Assessment 7/1/97 i

f Byron /Braidwood DBI Complete End of 1998 l

LaSalle DBI Complete 3rd Quarter,1999 l

Dresden/ Quad Cities / Zion DBI Complete End of 2000 l

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Indicator: UFSAR Chapter Starts Workoff Curve

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Most Significant PIF's Station PIF #

Description Discussion Operable Reportable i

Braidwood 1997-UFSAR Chapter 3 Confusion between requirements of Yes No 03414 Seismic Reanalysis UFSAR and an additional analysis reviewed by the NRC during the license process. Plant uses UFSAR criteria for design and not the criteria based on additional analyses. The licensing basis appeare, unclear as to which methodology should be used on an ongoing basis. (There are no operability concems).

Byron Following UFSAR Chapter 3 Same as Braidwood Yes No Braidwood Seismic Reanalysis Dresden 1997-Reactor Building Post Temperatures were shown as Normal Yes No 03354 LOCA temperatures Operating, EQ of components may be impacted Post LOCA. Analysis of Post LOCA conditions is being reconstituted.

Operability Evaluation 97-53 was performed that resulted in a " Operable but Degraded" status. Data from Browns

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Ferry and LaSalle demonstrated that SR equipment located in the RB and performing safety functions during post DBA will be functional at elevated temperature.

NRCMeeting 9/24/97 11

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Most Significant PIF's (continued)

Station PIF #

Detscription Discussion Operable Reportable Dresden 1997-SQUG SSEL does not in the case of a Dam failure, certain Yes No 05002.

contain certa:n equipment necessary to support the equipment to support CCWS system were not included in the containment CCSW SQUG SSEL CCWS was chosen as the system following a Dam decay heat removal path for SOUG failure resolution of USI A-46 (GL-97-02). This equipment should liave been identified on the SQUG SSEL for seismic evaluation. Dresden determined they are in compliance with their design basis and therefore there are no reportability or operability concerns by not having this additional equipment in the SSEL Dresden 1997-CCSW Pump Suction New Tech Spec identified a rninimum Yes No 12048 Minimum Water Level water level that is incorrect. The level of the intake bay is currently monitored and action is taken at a level above the identified tech spec level. The only other event that could lead to a significant immediate water level decrease is Dam failure, which requires specific actions to maintain the CCSW pumps as operable (DOA-010-01)."

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Conclusions

+ Discrepancies identified at Comed plants are similar to the issues identified in samples performed in response to NEI 96-05.

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+Baselining against other utility programs and NRC A/E audits to determine best practices.

l Our program addresses the "best practices" l

of the other utilities and should address most l

of the concerns being identified in the A/E l

audits.

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NRCMeeting 9/24/97 14

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Measurements

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Engineering Metrics 1

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ENGINEERING INDICATOR HIERARCHY Key 5 - Safety P-Production C - Cost Q. Quality N t0 Report Executives P-Engr. %

NRC No. Open. No. Closed & Totalsh No. Open, to.

Q.S-Salery Synem Perform S-Temp Aks.

No. Open, No. Closed & Totals /W Q.5-EAG indicators, Measure and Significance of Resects S. C-Fuel Performance. No. of Lenkers. Cost Russ Freeman Wiii Discuss from a Site VP S - Training Gonis, % Personnel Completed Training Engmeering VP Site Engmeering Perspective S. Q-Operability Assessments. Tracks the No ofOp. Assess.

C-O&M Hodget.

Badget. Monthly Aggregate.& Desiarion C.P-Soccess of Peer Group initiatives. Skd Pmcess. Temp hk4 i

5 - Operstor Work Arour ds - Work Off Ciarse S - Temporary Alterstions - Reduce to < 20 active P - Engine 2ing Recpsests - Maintain a 2-3 month backlog S - Modifications - Eliminate Old Mods 5 - Operability Assessments - None Greater Than One Refueling Cstle P - Design Packages - Deliver 6 months price to Outage C. P. Q. S-Comrmt for Resuhs - Goals NRCMeeting 9/24/97 17

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, PUBLICATION and FORMAL USAGE OF ENGINEERING INDICATORS i

Emeenthes i

f4.54 (f) Report NRC

~5LC Meetmg Nuclear Engineering Quality Osersiew Report, f

NFS Report Site VP Engineering VP Ouarterly Engmeermg I

Accountability Meetng 1

I SEM/ Station Meathly Repects Site Engieeering M aangers

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Engmeercg Team Meetings l

Management Resiew Meetings 4

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Station Bessiness Plaa i

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l Engineering Assurance Group i

+ Common station charters

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- common core product overview i

- station specific additions l

+ Common desktop instruction for reviews

+ Common "binning" of discrepancies

+ Meet as a Peer Group Monthly to Share

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Engineering Assurance Scope l

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+ Reviews Safety Evaluations and l

Operability Assessments, including those generated by Operations

+ Reviews significant calculations, including a l

sample of AE Calculations i

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+ Reviews a sample of DCPs, Temp Alts, and l

other Engineering Deliverables I

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l Engineering Assurance Grading Scale i

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1 No comment reviewed product acceptable as presented e

2 Comments that would improve the quality of the product, however, the product as presented was acceptable.

i 3 Requires revision to incorporate comments. PIF should be l

considered if product is completed.

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l 4 Erosion of Margin, requires revision to assure adequacy for j

present use. PIF must be generated if product is completed.

5 Potential Violation of design or licensing basis. Major oversight, requires revision to assure adequacy for present use. PIF must be generated if product is completed.

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NRCMeeting 92 U97 22

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NRCMeeting 9/24/97 26

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C a Ic u la tio n s 1oo%

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Calculation Review Results l

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+ Weaknesses in NEP Series of procedures for processing calculations identified by EAG and j

changes were incorporated in latest revision by the j

CCPG.

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+ " Good Cale" workshops being conducted 'with design i

engineers with very positive feedback being received.

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+ EAG has met with Engineering Supervisors and l

Leads to discuss EAG observations, past findings, j

and to explore methods for improvement.

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+ Specific feedback discussed at Site " Tailgate" Sessions

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+ Additional ESPT training on Calculations, Safety I

l Evaluations, and EAG Findings.

COE11Ecl NRCMeeting 9/24/97 28

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SLMMARY l

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+ The overall product reject rate for Engineering reduced from 35% in April to 17% for August.

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+ Offsite Review of Safety Evaluations and l

Operability Assessments also support the l

l improvements j

+ Three of Four Indicators making positive moves l

towards higher standards l

+ Focus remains on Calculation Quality. EAG l

Peer Group to analyze data across sites and recommend further actions l

NRCMeeting 9/24/97 29

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NRCMeeting 9/24/97 41

~~~

Conclusions

+ At Dresden Station indicators are required to be established for key work activities

+ Within Engineering, the indicators are widely promulgated and discussed at:

- Quarterly Engineering Continuing Training

- Monthly Management Meetings

- Weekly Engineering Accountability Meetings

+ Management " steers the ship" based on the indicators NRCMeeting 9/24/97 42

~ ~ ~

Closing Remarks i

1. Are We Improving and Influencing Plant Safety?

1 Safety System Performance 8

TempAlts & Operator Workarounds O

I Plant Capability (D/QC/Ry/Br) 8 Engineering Decisions:

8 I

SG Replacement / Merlin Gerin Breakers

==

Conclusion:==

Yes l

2. Are We Defending the Design Basis by Finding Problems?

Engineering PIFs 8

Design Basis LERs 8

l SSFI's / Assessments (LaS system reviews) 8 DBI 8

==

Conclusion:==

Yes / More discovery will occur

3. Are We Delivering Cost Effective, High Quality Products Predictably?

3 Costs o

f l

Predictability o

j EAG Quality Indicators 8

I i

==

Conclusion:==

This is Engineering's Biggest Need for Focus & Imp.rovement and This is Our Focus for 1998.

NRCMeeting 9/24/97 43

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NRCMeeting 9/24/97 44

- ~,

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r F.

Dresden Nuclear Power Station Auxiliary Systems Condensate Domineralizers JULY 1997 r:r%rw i+,..

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L._a Previous Performance PER*ORMANCE

SUMMARY

Number lesue Prioetty Act. Nn PHYSICAL CONDITION I CONDmON MON (TORING

SUMMARY

Number leeue Priority Act. Nn DERATING

SUMMARY

l Number M W Loss Event Priority Act. Nn WORK BACKLOG

SUMMARY

Number Late PM 6-24 Mo.

> 24 Mo.

Priority Act. Plan 1

0 0

11 No No i

11 Corrective & Prevenhtsve WR's older that 24 Monthe l

WORKAROUND

SUMMARY

Number leeue Prtortty Act. Plan DESIGN SUtWARY:

Number leeue Priority Act. Plan 1

TALT # 2 55 95, installed 12/19/95. Test e pressure releef or venting for the Max No Yes and Hold Tank drain hne on the Cond. Domin. System l

2 TALT

  • 2 28 96, installed 2/17/97. Provide jumper on pressure switch to allow No Yes l

use of U3 eir Compressor to transfer resin while U2 is OOS. This Temp Att was removed 1/31/97, but was reinstalled on 2/17/97, i

,,

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