ML17187A931

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Refers to 970228 Meeting in Lisle,Il Re Status of Actions Related to NRC Confirmatory Action Ltr RIII-96-16.List of Attendees & Licensee Presentation Encl
ML17187A931
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 04/09/1997
From: Kropp W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Jamila Perry
COMMONWEALTH EDISON CO.
References
CAL-RIII-96-16, NUDOCS 9704220327
Download: ML17187A931 (58)
v • d • e


Text

Mr: J. S. Perry Site.Vice President Dresden Station

....:*=:!~**

~~-

Commonwealth Edison Company

  • 6500 North Dresden Road Morris, IL 60450 April 9, 1997

SUBJECT:

DRESDEN CONFIRMATORY ACTION LETTER MEETING

Dear Mr. Perry:

This refers to the *meeting conducted at the NRC Region Ill Office in Lisle, Illinois on February 28, 1997. This meeting was to discuss the status of your-actions related to the NRC Confirmatory Action Letter (CAL) No. Rlll-96-016.

In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal R_egulations, a copy of this letter and the enclosures (the agenda and handouts provided by your staff at the meeting) will be placed in the NRC's Public Document Room.

We appreciate your cooperation in this matter. If you have any questions regarding this meeting, please contact me at 630/829-9603.

Docket No. 50-237 Docket No. 50-349

Enclosure:

1.

Attendance List Sincerely,

!/s/ w. J. Kropp Wayne J. Kropp, Chief Reactor Projects Branch 1

2.

Licensee Presentation, Dresden Station Presentation to NRC on Status of CAL Action Items Document: A:\\CALMTG;228 To receive a copy of this document, indicate in the box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE Riii~ le I

I I

NAME Kropp/c~

DATE 04/'f/97 OFFICIAL RECORD COPY If I

\\

9704220327" 970409 J -~

---~D~--~DOCK 0500~B~7 l J

....;:~ --

I 1111m !Im 111~ 11111~11111m 1J111111

J. cc w/encl:

T. J. Maiman, Senior Vice.President Distribution:

Nuclear Operations Division D. A. Sager, Vice President, Generation Support H. W. Keiser, Chief Nuclear Operating Officer T. Nauman, Station Manager Unit 1 M. Heffley, Station Manager Units 2 and 3 F. Spangenberg, Regulatory Assurance Manager I. Johnson, Acting Nuclear

  • Regulatory Services Manager Richard Hubbard Nathan Schloss, Economist Office of the Attorney General State Liaison Officer Chairman, Illinois Commerce Commission Document Control Desk-Licensing Docket File w /encl PUBLIC JE 0 1..w/encl DRP w/el)CI Project Manager,. NRR w/encl Riii PRR w/end CAA 1 w/encl (E-Mail)

A. B. Beach, w /encl Riii Enf. Coordinator, w /encl DRS (2) w /encl Project Manager Unit 1, NRR w/encl' -

OC/LFDCB w/encl SRI LaSalle, Dresden, Quad Cities w /encl RAC 1 (E-Mail)

Deputy R~, w /encl TSS w/encl

DRESDEN CONFIRMATORY ACTION LETTER

. MEETING.

REC'D W/LTR DTD 04/09/97.... 9704220327

- NOTICE -

THE ATIACHED FILES ARE OFFICIAL RECORDS OF THE INFORMATION &

RECORDS MANAGEMENT BRANCH.

THEY HAVE BEEN CHARGED TO YOU

. FOR A LIMITED TIME PERIOD AND.

MUSTBERETURNEDTOTHE RECORDS & ARCHIVES SERVICES,

SECTION, TS C3.. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT FOR REPRODUCTION MUST BE.

REFERRED TO FILE PERSOt*JNEL.

- NOTICE -

  • (

ATTENDANCE LIST.

Commonwealth Edison (ComEd>

J. s. Perry, Dresden Station Site Vice President J. M. Heffley, Dresden Station Manager K. W; Frehafer, Dresden Engineering Assurance Group R. D. Freeman, Dresden Station Site Engineering Manager F. A. Spangenberg, Dresden Regulatory Assurance Manager

  • E.

Connell, Dresden Station Design Engineering Superintendent Nuclear Regulatory Commission G. E. Grant, Director, Division of Reactor Safety (DRS), Riii W. J. Kropp, Chief, DRS, Engineering Specialists Branch 1, Riii R. N: Gardner, Chief, DRS, Engineering Specialists Branch 2, Riii M. A. Ring, Chief, DRS, Lead Engineers Branch, Riii P. L. Hiland, Chief, Reactor Projects Branch 1, Riii *

~ R. A. Capra, Director, Project*Directorate 111-2, NRR J. S. Stang, Dresden Senior: Project Manager, NRR

ENCLOSURE 2 ComEd DRESDEN STATION February 28, 1997

ComEd DRESDEN STATION Russell Freeman Kenneth Frehafer Edward Connell Robert Renuart AGENDA Introduction I Opening Rem~rks Update of Activities for the Dresden Engineering Assurance Group (DEAG)

Duties & Expectations for an Independent EAG Status of Key Parameter Screenirig for Twelve Systems A Walk-Through of One System Key Parameter Screening Evaluation of s*ignificance ofCalculational Errors Including Operability Significance and Scope of Reduced Margin Design Calculation Discrepancies Found In The.Sargent & Lundy Calculations

  • Corporate Engine~ring.Activity Status of The Sargent & Lundy Review ofECCS, HV AC, and Service Water Calcufations At Other Six Sites...

EAG Peer Group Charter NEP and Flow Chart for a Design Basis Documentation Conflict

,(11

ComEd DRESDEN STATION Carl Richards/".

Edward Netzel Russell Freeman All

.*AGENDA{continued)

Corporate Quality V eri~cation Activity.

Siemens.Audit Bechtel Audit

  • Closing Remarks Open Discussion

. I

  • ~..

ComEd.

DRESDEN STATION Engineering R. D.,Freeman

' ~

  • * * *..
  • Site Engineering Manager

I' ComEd" DRESDEN STATION*

Dresden* Engineering Assurance Group Ken.Frehaf er.

ComEd***

DEAGStatus DRESDEN STATION

  • Revised Procedure to Include PIFs. *
  • SignificatJ-t Work Activities.

- TwelVe System Paraineter Screening Review.*.

~

-.. *Finished review of o*pen mod 50.. 59s.

. - *D3Rl 4 modification review on-going.

- Instrument Uncertainty.Issues.

  • ._- Provided input to ISI. report.

-Reviewed-.iriputs to D*3R14 reload analysis.

-*:~

. ComEd

  • DEAG Status (continued)

DRESDEN STATION

  • 32 Engine,ering Products Reviewed.

- 12 system screen Operabilities.

- Torus *water level instrument Operability.

- Elevated Torus temp Operability.

  • Nine Products Required Re-Work.

-

  • Inputs not ref ~re~ced. *

~ Math errors (in conserVative.direction).

  • *'* -~-

ComEd. DEAG Status (continued)

  • DRESDEN STATION
  • PositiVe Observations. *.

- Intra.-discipline communications improving.

  • Areas* for Impr9vement.. :

- Safety Evaluations. *

~ Attention to detail.

ComEd.*

DRESDEN STATIQN Screening of Key Paralneters For Twelve Risk Significant Systems E. C. Connell, III

. Design Etigineering Superintendent

I*~

,.. - ~-

"ComEd.

ComEd Commitments*

DRESDEN STATION

~~~*%?£

  • ~xhG *

~*u; r**~~~;~~~~~~~

  • Screening.of key operating parameters on the twelve systems most important froin a risk perspective to verify that calculations exist to support.those para~e.ters by*February 28, 1997
  • The NRC will. be immediately informed if critical parameters on* an.y of the twelve systems. are -

discovered to be. outs.ide* of normal acceptance *

. values * * * * * *

  • . Results of the. screening will be provided to the NRC on a monthly basis. through a meeting and docketed response

ComEd Presentation Outline

  • DRESDEN STATION
  • Walk Through CCSW Key Parameter Matrix *
  • Discrepancy Summary *
  • Summary. of Fin*di:Qgs
  • Use and Maintenance of Key Parameters.

ComEd DRESDEN STATION

. Walk Through CCSW Key Parameter Matrix

  • System Description.
  • Key System (;Omponetits
  • Operational Modes
  • .Key _Par*ameters and Bas.is
  • *Dis*crepancies.
  • References
  • Calculation List *

.*. I CONTAINMENT COOLING SERVICE WATER (CCSW)

System Description

The CCSW system provides cooling water to tube side of the LPCI/CCSW Heat Exchangers to remove heat from the primary containment. The. function of cooling the water in the suppression pool, thereby limiting the temperature of the suppression pool water, assures the following:

- cooling of the Containment..

  • - no radioactive release through the containment heat exchanger The CCSW system is ap open loop system coqsisting of pumps, heat exchangers, valves, and associated piping and controls. The pumps take* suction ~om the crib house bay and circulate water through the containment heat exchanger to cool S\\lppression pool water. The water is then discharged to the Service Water main header. The CCSW system circulates water through room coolers to maintain the temperature inside a watertight vault that contains two of the four CCSW pumps for flood protection. The CCSW system also provides a safety *related source of cooling water to the control room air conditioning condensers.

Key System Components Component EPN 2(3)-:1501-44A 2(3}1501-448 2(3)-1501-44C

. 2(3)-1501-440 2(3)-1503A 2(3)-15038.

2(3)-5700-30A 2(3)-5700-308 2(3)-5700-30C 2(3)-S700-30D.

2(3)-JS43-A 2(3}1543-8 2(3}1501-3A 2(3)-1501-38 Operational Mod_es

  • Conla}nm,ent Spray Mode Initiation Manually initiated Function Description :

C,CSW A Pump.

CCSW8Pump CCSWCPump

. CCSWDPump LPCl/CCSW A Heat Exchanger LPCl/CCSW B Heat Exchanger CCSW Vault Room A Coil CCSW Vault Room B Coil CCSW Vault Room C Coil CCSW Vault Room D Coil Pressure Differential Sensor fressure Differential Sensor CCSW Flow Control Valve CCSW Flow Control Valve CCSW provides cooling water to the tube side of heat exchangers 2(3)-1503A,B to *cool the water in the suppression pool.. Suppression pool water is circulated through the shell side of the he~t exchangers by the Low Pressiire Coolant Injection (LPCO system to spray nozzles in the containment. Minimum number of pumps in operation: 2 CCSW and 1 LPCI.

Suppression Pool Cooling Mode No unique requirements except; pumps in operation are: 2 CCSW and 2 LPCI pumps and LPCI flow is returned to the suppression pool.

  • D-28

Station Blackout Mode No additional requirements.

Appendix R Mode No additional requirements Dam Failure Mode Similar to modes above exceptUSFAR section 9.2.5.3.2 implies only 1 CCSW pump is required. This is contrary to Section 9.2.1.3 which calls for a minimum of 2 CCSW pumps. See Potential Discrepancy item 5.

Cold Shutdown using Safety Grade Systems Mode

  • The CCSW system and pressure relief system are used in conjunction with the LPCI system to provide

_: : a means of achieving cold shut down using safety grade systems. See UFSAR Section 6.3.1.2.

Key Operation Parameters Parameter

~

Maximum service inlet water temperature 75~

Parameter Reference 26 Minimum Water Source, 500ITMean 2

Elevation

  • Containment Spray Mode fuml2 2(3)-1501-44 A.B,C,D Flow (Two Pumps)

Net Positive Suction Head Required Sea Level 5600 gpm 18 ft

@3,500 gpm/pump

  • Sec.

(3.8 C) 26 9

Calculation

&eference No calc. is required. This is a boundary condition on the system.

Note:.A licensing amendment was submitted to the NRC on Feb 17, 1997 which will raise.the maximium tempe~e to 95° F.

  • No calc:is required. This is a boundary-condition on the system:

Note: See. Potential ~iscrepancy item 1.

DRE96-0214Rev.O 11/12196 Unit2/3

. "Minimum Available CCSW flow to maintain a 20 pi differential between LPCI and CCSW,in CCSW H~t Exchanger" Note: A licensing amendm~nt was submitted to the NRC on Feb 17, 1997 which will lower the flow raie to 5000 gpm.

No calcuiation was found.

Note: See Potential Discrepancy item 2.

D-29.

Parameter

~ eai:am1:t1:r Reference CCSW Pump Motor Rating 500HP 17 Tenninal Voltage 4000 Volts 18 Suppression Pool Coolini= Mode Fl9w (Two Pumps)

. Heat Exch!Uli=er 2(3)-1501-44 A,B~C,D 5600 gpm 26 Heat Transfer Duty 98.6 MBtu/hr 27

@Tube Side Inlet

  • 95° F 27

@Tube Side Flow 7;000 gpm 27

@Sh~ll Side Temp

'165° F.

27

@Shell Side Inlet 10,700 gpm 27 Note: These parameters and-the physical data characterize.the heat exchanger performance.

and are used to detemiine the heat transferred under actual operating conditions. For*the design basis calculation5 the LPCI flow is

  • 5000gpm !Uld the CCSW flow is 5600 gpm.

Vault Room Maximum Temperatlire Vault Room Coil 2(3)-5700-30A,B,C,D

.. Cooler Coils /Cooler 120°F

2.

See*

Note 1

Sec.9.2 (Fig.

. 9.2-1, 9.2-2)

Calculation Reference No calculation was found.

Note: See Potential Discrep!Ulcy item 3.

No calculation was found.

Note: See Potential Discrep!Ulcy item 3..

Same as Contairunent Spray M9de Flow shown

  • above. The hydraulic conditions are the same.

S. Mintz to S. L. Eldridge et al " Dresden LPCl/C::ontairunent Cooling System - Comparisori of Heat ExcbMger Heat Transfer Rates." 12128/92 VV-l3 RevO 5nl93 Units2/3 "CCSW vault cooler perfonnance and effectiveness" Note: The calculation VV-13-shows that the max.

. vault temperature will be well below 120° F. This then became the de facto te~perature limit No calc. is required. This is a statement of fact D-30

Parameter.

Total Flow Fc;>r Two Coils 2-5700-30 A,B M~.T1::nninal Voltage 2-5700-30 C,D Min.Tem1inal Voltage 3-.5700-30 A,B Min.Tenilinal Voltage 3:..5700-30 C;D.

Min.Terminal Voltage 110 gpm Parameter Reference 7

Calculation Reference A TD-0253 Rev.O Units 2&3 Mar 5, 1993 "Determination-of Flow Restricting Orifices for CCSW Pump Room Coolers and CR Refrigeration Condenser in the CCSW System" Note: Flow does not pass through flow meter 9198-18-19-1Rev.1 *

"Startiilg and Running Voltages" Note: This calculation determines the terminal voltages under starting and run conditions and shows that these voltages are acceptable.

9198-18-19-2Rev. 1 "Starting and Running Voltages" Note: This calc.ulation d~termines the terminal voltages under starting and rim conditions and shows that these voltages are acceptable.

9198-18-19-3 Rev. 1 "Starting and Running Voltages" Note: This calculation determines the terminal voltages under starting and run conditions and shows that these VQltages are ~cceptable.

9198-18-19-4 Rev. 1 "Starting and Rwining Voltages" Note: This calculation determines the terminal voltages under starting and run conditions and shows that these voltages are acceptable. Except as noted below.

D-31

Parameter Parameter Reference Calculation Reference Note: The running terminal voltage was found to be 89 % instead of90 %_.To reconcile this difference calculation 9198-18-19-6 Rev. 0 was prepared to justify accepting the lower voltage Control Room HYAC 102 gpm 8

ATD-0253 Rev.OUnits 2&3 Mar 5,1993 "Determination of Flow Restricting Orifices for

  • Refrigeration Condensing (Unit 2 only)

Unit CRCU) Flow

. CCSW Pump Room Coolers and CR Refrigeration Condenser in the CCSW System" Note: This calculation shows that the room cooler arid CR Refrigeration orifices were ~.ized for 55 gpm per cooler.and 102 gpQl respectively.

Note: Flow does not go through CCSW flow meter:

  • It can be measured by a meter in the CR.. HV AC '

System. However, during surveillance testing there

. is no HY AC. condenser flow. Therefore, to have a valid test, the flow required must include the aCtµat HY AC condenser flow. This is reported to be 121.

gpm.

ccswa.PCI Differential Pressure Sensor:

2(3)-154J-A)3

  • ~o psi 6

DRE96-0214Rev,O 11/12/97 Unit 213 1

  • ~Minimum Available CCSW flow (Sec. 6.2.2) * *.to maintain a 20 psi differential between LPCI and CCSW in CCSW Heat Exclianger" Note: Calculation DRE 96-214 demonstrates that for the i *LPCI fl. CCSW case the CCSW pre~sure diff erentiai can be maintained 20 psi above LPCI for a range of containment pressures. These calculations should be extended to cover the 2 *LPCI

/ 2 CCSW case. It can be shown that the 20 psi can

  • be maµitained for these cases but quantitatively ~e flow.rates are not known and hence the effectiveness of the containment heat exchanger is

. not known. All of which. means.that the long term temperature and pressure of the contaiIµnent canliot be predicted. The analyzed.case covers the limiting containment cooling case from a licensing standpoint. However, the other cases are shown in section 6.2 of the USFAR as illus~tions of capability and should be corrected.

See.Potential Discrepancy.item 8 ofLi>CI Key Parameters-(Table 2a).

0-32

I l

Parameter CCSW Flow Control Yalye 2(3)-15Ql-3A,B Min. Operator Terminal Voltage Unit 2 Valve A Unit 2 Valve B Unit 3 Valve A.

Unit 3 Valve B

  • 425 Volts 424 Volts

. 431 Volts 434 Volts Potential Discrepancies Parameter Reference 24 Calculation Reference The reason why a 20 psi differential is adequate can not be found in a calculation. A calculation has been performed by C. B. Johnson and F. J. Mollerus that shows the 20 psi is adequate. This. calc should be reviewed and adopted by ComEd.

See Potential Discrepancy item 4.

004-MN-344, Rev 8, 5/6/93 "Thrust Windows Calculation for Functional Gr9up LPCI l;"

  • 1. *Section 3.19.2 of the Dresden Technical Administrative Requirements (I?A TR) identifies the minimum
  • water level in cribhouse CCSW suction bay of 499' - O". However;* section 3.8.C.1 of the TSUP identifies
  • the minim~ water level as 500' - O". furthermore, the RUFSAR references drawing M-IQ which states the rtormal operating low water level 'in the suction bay iS 501 ',. O'\\ and this value was used in calculation DRE96*0214.
2. No formal calculations ex~ that demonstrate adequate Net Positive Suction Head (NPSH) is available to the CCSW pumps.
3. No calculations could be found that demonstrate there is sufficient motor terminal voltage for the CCSW

,..

  • pumps so the pumps ca.it perform adequately. In addition, no calculations have been found that' show the CCSW pump motors are matched_ for power and Speed requirements to the CCSW :pumps.
4. There is a requirement that the CCSW side of the containment cooling heat exchanger be maintained at.

20 psi above the LPCI side of the heat exchanger to preclude leakage fro'm LPCI to CCSW.. A. report was generated by F. J. Mollerus and C. 13. Johnson that-shows why maintaining this pressure differential is adequate. This report should be formalized into a calculation.

5. Section 9.2.1.3 of the RUFSAR specifies the minimum requirements for containment coo_iing include 2 CCSW pumps. However, section 9.2.5.3.2 indicate only 1 CCSW pump will be available during a postulated dam failure. Currently there are no containment cooling or heat exchanger di1:ferential pressure calculations for a 1 CCSW pump scenario.

Parameter References

l.

Dresden Reb<1:5Cline Updated Final Safety Analysis ~eport (UfSAR)

2.

Dresden Station Unit 2 & 3 Technical Specifications Upgrade (TSUP)

3.

D.resden Station Unit 2 & 3 Technical Specifications Upgrade Basis (TSUP Basis) January.13, 1997 D-33

\\

4.

Dresden Administrative Technical Requirements (DA TR) September

5.

Dresden Technical Specifications December, 1996

6.
  • Memo.: J. W. Dingler to R. J. Goebbert 02-19-93 "20 psid Differential Pressure Setpoint Between CCSW and LPCI Across LPCI HX" Ref06.028 to Design Basis Document 1.72:

. 7.

VV-11 Rev 0 Feb/8/92,"Determine CCSW cooler cooling coil's new capacity using test data."

8.

D. H. Lagler to C. W. Schroeder Nov 9, 1992 "Dresden - Unit 2 Finalized Operability Determination of the CCSW Pumps" Ref06.055 to Design Basis DocumentJ72:

9.

"CCSW pump curve-NPSH" Ref03.014 to Design Basis Document 172:

10.

K. W. Hess to D. P. Galle Aug. 13, 1974 "Containment Cooling Water Pumps(CCSW) Technical Specification Change" Ref 06.004 to Design Basis Document 172:

l 1.

LPCI Pump Curv.e by Bingham Pump Co. Jan 10, 1968

12.

EMF-89~65 Rev. 3 July 1_995 "Dresden Units 2 and 3 Principal LOCA Analysis Parameters"

13. 729E583 Rev 1 1968 "Process Diagram:LPCI Containment Cooling System"
14. 251HA654 Rev. 3 Aprll 15~ 1969 "At1Xiliary System Data Book"

. 15.. Memo to DBD DRF by W. G. Myers et al March 4, 1992 "BWR 2, 3, 4, 8l. 5 R,HR.-Containment Spray Cooling (CSC) Requirements" Ref 06.100 to Design Basis Document 172"

16.

NEO..EIC-MOV~DR-0003 Rev*. 0 Sept I, 94 "MQV Temiinal V.oltage "c~leulation"

  • 17~ "MOV Termfual Voltage Calculation"C.N.Mathewson.to R. J. Ascherai Feb. 25, 1971 "Containment Cooling Service Water Pumps-, Motor Ratings Ref 06.008 ti) Design Ba5is Document 172:
18. Memo of Data Transmittal GE to S &L 4/8/68 S&L P.O. NO. 3447-134
19.

21A5580 Rev 4 Oct. 31 ~972 "Motor General Requireµients"

20.

Containm~nt Cooling Heat Exchanger Specification Sheet March 29*1967 By Berlin Chapman Inc.

21. CHRON # 0306316 K. Simmons to R.L.Bax et al March 24, 1995 "Orifice In Min Flow Lines I LPCI and Core Spray Systems" 22 257HA350AM Rev. 10 l l/9nl "Nuclear Boiler System - Data Sheets.

23; DRE96-()010 Rev.0 l/16/96"Motor Terminal Voltage Cale. for Dresden Unit 2 MOV's 2-0202-5AIB" 24 NED-EIC-MOV-DR-0001 REV 0 8/2/94"Valve ActUator Motor V9ltage Calculation for Dresden 1501 System Units 2&3"

25.

DRE96-01~7 REV 0 7/8/96"Motor Terminal Voltage Calculation for Dresden Unit 3 MOVs 3-1501-21A/B" 034

~

. l ti,~

. 26.

Amendment No. 152 to Facility Operating License*No. DPR-19 and Amendment No. 147 to Facility Operating License No. DPR-25. Jan 1997.

27 S. Mintz to S. L. Eldridge I B. M. Viehl "Dresden LPCl/Containment Cooling System - Comparison

. ofHaet Exchanger Heat Transfer Rates." Dec.28,1992 Calculation References

1.

UFSAR Log# D.FL-96-140 1/13/97

2.

DRE96-0214Rev.O }J/12197 Unit 213'.'Minimum Available CCSW flow to maintain a 20 psi' differential between LPCI and CCSW in CCSW Heat Exchanger"

3.

NED7M-MSD-45 Rev. 0 12131/92 Units 2/3"Do:sden Unit 2 LPCI Heat Exchanger Mode C Heat.

Ex~hanger Duty Calculatio.n"

4.

VV-13 *Rev 0 5nt93 Units 213"CCSW.vault cooier performance and effectiveness"

5.

ATD-02S3 Rev.O Units 2&3 Mar*S,1993"Detenrtination of Flow Restricting OrificesforCCSW

  • Pump Room Coolers *and CR Refrigeration Condenser in the CCSW System"
6.

9198,.18~19-l Rev. 1 "Startjng an4 Running Voltages" 035

ComEd.

CCSW: Discrepancy #1 DRESDEN STATION

  • Minimum water level in the crib house is 499'-0 in DATR; 500'-0 in TSUP, 501 '-0

in Drw M-10 re*ferenced in the UFSAR and 501 '-0 in Calculations D.RE96-0214 Rev. 0 performed to supp_ort. ISI response

- The current water level in the crib house is

>501'-0

- 2/17 /97 licensing amendment calculations *

(DRE96-0214_Re.v. 1) uses 500'-0"

- n*A TR and M-10 will be revised (NTS #23 7-140-97-00901)

ComEd...

  • CCSW: Discrepancy #2 DRESDEN STATION
  • No formal Calculations to Demonstrate Adequate NPSH is Available for CCSW Pumps

- Surveillance* Testing.;has.been performed for pump flow of approximately 3,500 gpm. The design basis flow is 2,800 gpm.

- The pumps are located* at.E 495' and with the _500' min water level. Based on engineering judgement,

. there is adequ-ate NPSH available to meet the 18'

- Corrective Action will be implemented under NTS

ComEd CCSW: Discrepancy #3 DRESDEN STATION

  • No calculations to show that adequate terminal voltage for the CCSW*motor is* available and that the motor is sized correctly for the CCSW pump

- The surveillance tests to 3,500 gpm vs 2,800 gpm for the design basis, verifies the adequacy of the pump motor size

- The surveillance tests also verify that adequate voltage is available at the terminals to drive the motor when off site power is available -

-- DGA ~ 12 lists -manual operator.actions to ensure* availability of CCSW system _d~ring LOOP and LOCA.

- The correction action will be* tracked under NTS

ComEd

. **....*. CCSW: *Discrepancy #4 DRESDEN STATION

  • The basis for the 20 psi differential pressure for the* LPCI/CCSW Hx to prevent out
  • leakage not. available

- An evaluation was prepared which shows that 20 psi differential press:ure is adequate

  • __ Corrective action under NTS

COmEd CCSW: **Discrepancy #5 DRESDEN STATION tr~Ji*~~~~~*~~~~~~~-i¥,~~~~'l!l'~!1~~1i~'ffi'l1'~fti(t1t1~~\\i¥'1P'.~jf~f.>i**t;~:~%i~*ti'.'.*~11;::,;*

  • The Dam break case postulates the simultaneous occurrence of an earthquake, a dam failure, a LOOP and a LOCA in,one unit. -No_ calclllation exists for containment cooling or differential pressure requirements for this case..

---* Section 9.2*.-5.3.2 describes this scenario and.a

  • copi_ng mechanism*for it which requires the flooding *
  • of the-containment

- Corrective action. tracked* under NTS..

ComEd Summary of Findings DRESDEN STATION

'¥

  • For the Twelve Systems reviewed a total of 56 Ifs were initiated.. Only one resulted in Degraded Plant Operability or *system Being*

Declared *1~operable.

  • Discr.~pancies identified during the Key Parameter Sc~eening
  • a*:re similar to th.ose identified during the Dresden self assessment and the NRC ISl

ComEd Summary of Findings DRESDEN STATION

. (Continued) *.

  • ISi Co*rrective Actions are adequate to address

.. the finding

- Engineering Assurance Group Overview

~ NEPs Revisions

- Review of UFSAR requirement against Design Basis Documents*

~ For the: 12 Risk Significant Systems, Reconstitution or Validation of Calculations:

  • Portions of ~ystems affected by modifications*
  • Missing or incomplete_ key calculations
    • .1.*..

DRESDEN STATION Use and Maintenance of Key Parameter Matrices ComEd

  • ESP Training on 12,Systems Key Parameters in March '97 for al~ Dresden Engineering staff
  • Procedure for Key Parameter.Matrix Maintenance and its use.by Systerp. Engineers and Design Engineers will be Developed
  • The Key Parame.ter Results will be-the *starting* point for the. 'Adequacy and *R~tri~vability of Design Basis' Project

. ComEd DRESDEN STATION Disposition of S&L Calculation Audit Findings

  • E. C. Connell, III.

Design Engineering S-µperintendent

ComEd

  • .* Significance Level DRESDEN STATION
  • Significance I,evel
  • Description

- 0 Editorial*

- 1 No Impact on Design Margin

  • -* 2 Potential Impact on Design Margin

- 3

. Design Margin Eroded

- 4 Design Margin Exceeded

~.

ComEd DRESDEN STATION Area Observation ltl!Hl£*b4*111*1, l'<eV. U IB9o£-17*19-1, Rev. o 18982-64-19*2, Rev. o IM12-J-95-uu..

1:1:11111*31*1!1*1, l'<eV. 0 ltl.<;><>*11*111*1, l'<eV. U 10.,....... 1-111-1, l'<ev. l IVR-10, Rev. 1

.... /.

IVK-1 /,Kev. 0 IMt't:U llllZ1*9:1*uu, l'<eV. U WMt:U tl9tlZ*bZ-UZ, l'<ev.*U 1u:i111-.. 111-uu... l'<ev. £ IDKt:96-01J4, Kev. 0 WMt:U a:i*t:* llZ-Ul, l'<ev. u 19Z1:1*111*U£, l'<ev. U u.. 515 11/0ti*OO*t:U-::;, l'<ev. {

t111uu-1:i-t:u-::;, l'<ev. 4 Ul'<t:*Mvv-:i, l'<ev. u Mt't:U 17<>.<l*lUU-UU, l'<ev. u t:MU Ubt.. df, l'<ev. u A I U*U£1 b, l'<eY. U A1u*U191,l'<eV.2 A I u*UZ:IJ, l'<eV. 1 Significance and Trending Matrix Accurate Organized Usable Comple.te Technical Legible I!'

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N/A I No Comments N/A INO comments N/A INo comments NIA INO 1,;omments N/A INO 1,;omments N/A I No comments x

x x

x x

J 1ca1c Kev1sed & Issued x

x x

x x

1 1uocumen1a11on

, 1uocumen1a11on 1

11.>rapn rev1sea oy 1,;omt:o x

x J

!Duke Revising Base Cale

.J<.

x 2

1ca1c Deing rev1sea Dy ::i&L 1

1uocumen1a11on x

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1 uocumentauon 1

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2 NO runner acuon requ1rea N/A NO 1,;omments x

x x

x x

x 3

1,;a1c vo1aea oy*::;&L per Com Ed uocumentat1on. Cale revised x*

1 by S&L. conclusion unaffected x

3 Cale revised Dy S&L.

conclusion unaffected

ComEd *.*Calculation* Review Summary*

DRESDEN STATION

  • 24 Calculations Reviewed by SQV

~ 6 Pre-identified with Errors*

  • 18 Randomly Selected*
  • . 6 Pre-jdentified Calculations - Significance Level 0 Level 4s 4 Level 3s
  • 0 Level 2s

...;. 2 Level ls

  • 18 Random Sample Calc.ulatio.ns - Significance Level 0 Level 4s 0 Level 3s
  • 2 Level2s 7 Level ls 1 Level* Os*

8 No Errors*.

  • /..

I

-~

DRESDEN STATION.

Calculation

  • . ATD-0253 Rev.* 1

.ComEd

  • Size. Orifices for CCSW Room Coolers
  • Used L'PCI Pu~p Curves.*_
  • Affected Calculations Only

..(.

DRESDEN STATION Calculation ATD-0216 Rev.* 0

  • CCSW Pipe Losses for *1992 Amendment

)

  • Used LPC-I Pu*mp CurVe
  • * -Calculation Cancelled I

ComEd..... Calculation* VR-10 Rev. 1 DRESDEN STATION

  • SBGT Air Changes I Day -
  • Minimum Charcoal Filter Efficiency 93%

/'

    • I- **

ComEd DRESDEN STATION Review of Impel/ Calculation 0591-387-003, Rev.2

  • Switchover From SBGT to Hardened Vent*
  • Concluded Ductwork Overpressurized at 25 psi
  • Affected DEOP

"-*. ~ -

t 1"

ComEd Conclusions

. DRESDEN STATION

  • No Significant Safety Impact
  • Greater Care Warranted in Future

ComEd-DRESDEN STATION Corporate* Engineering Activities

  • Bob Renuart*.

Chief Engineering, Configuration Manage~ent and_-

. --Engineerin*g Assurance "f:

ComEd.

DRESDEN STATION Status: of S&L Expanded

. Calculation Review

~iffi~"'~~~~~e~1¥m~J;~~mtB.Jtti1~~£~::;mJ1sfif::~~0iJ:;;~:~;,~;'.~'~,}~tt~*.*.

  • Reviewed all System Calculations Involving ECCS.,* SW, HVAC at all*stations
  • Reviewed Past Five Years
  • Total Population.. 150 calculations
  • Random sample of 50 calculations c

p

  • ~

ComEd DRESDEN STATION

  • Level.4 ~*Design Margin Exceeded
  • Level 3. Erosion of Design Margin

.

  • Level 2.
  • Potential Erosion on Design Margin

,\\

  • Lev~l 1 * = No Impact on Design Margin*

-

  • Level 0 =Editorial*

ComEd*

Status. ofS&L Expanded DRESDEN STATION Calculation Review

  • Level 4 = 0 findiQgs
  • Level 3 = 0
  • Level 2 *. 0
  • Level 1=20
  • Level 0 ~ 10
  • No Findings *. 20 *. '*.**

.*.. (*,

---~-

',I If.

DRESDEN STATION

. Status ofS&L Expanded Calculation Review ComEd

  • Level -1 Findings include:

- Undocumented assumptions

- Undocumented acceptance criteria

  • Undocu~ented design inputs -

---:-. Math Errors (No significant impact)

-*:Misc. Discrepancies *with Current Procedure Requirements

  • DRESDEN STATION Status o/S&L Expanded Calcultltion Review ComEd.
  • Level 0 Findings include:
  • - F*ormat

- Attachments

~

  • References Conclusion - Findings from expanded sample are similar in nature to ComEd's Random.Audit. Corrective actions taken following the ComEd Au*dit address these findings.

S&L EA Function, as well as Com~d follow-up Audit will confirm.effectiveness.of S&L;s.-_Corrective Actions*

~

ComEd.

.* Common Site EA Group

    • charter DRESDEN STATION Common Purpose of the EA Group

. The pu.rpose* of the EAG is** to provide oversight of

  • . engineering activities that validate, maintain, and if necessary, reconsti_tute the* Station's s design bases.

The E*AG will.al*so assure that engineering' products are in com.plian*ce with current license and design bases anq are.cons*istent with industry standards and

  • .methods.

'I l

-~

I

. ComEd Site EA Group Charter Common Oversight Roles DRESDEN STATION

  • Design Change Activities (mods, temp alts, setpoint changes)
  • Safety Evaluations.*
  • Licensee Event Reports
  • Calculations *.

Sampling varies from site lo site; however, all will review both Com Ed. and Contractor Products

1

{t

/

I l

ComEd *.

  • EA Peer Group Goals DRESDEN STATION
  • Champion Self Assessment
  • Establish minimum sampling of Oversight

. Activities.

  • Self Assess the EA Groups Across the Seven Sites
  • Facilitate Establishment of Common

~...

Perform.ance *Standards* and Metrics.

  • Support technical evaluation of Supplier*

Audits.

ComEd DRESDEN STATION ComEd NEP 1 Disposition of Design Bases Discrepancies 0-03

-1 DISCREPANCY IS BETWEEN UFSAR AND PLANT

. 1 WAS THE PLANT PROPERLY MODIFIED WITH A 50.59 EVALUATION?

v~.. -

UFSAR UPDATE PROBLEM EXISTS UPDATE THE UFSAR RELYING UPdN EARLIER 50.59 EVALUATION DISCREPANCY IDENTIFIED l

INITIATE A PROBLEM SCREEN PIF FOR IDENTIFICATION FORM OPERABILITY ISSUES 1

l DISCREPANCY IS BETWEEN DESIGN DOCUMENTS AND THE UFSAR l

VERIFY THAT UFSAR DOES THE UFSAR No IS CORRECT REFLECT THE LICENSING BASIS?

1 SELECT ONE.OF THE OPTIONS BELOW No Yea MODIFY THE PLANT CHANGE UFSAR

. UTILIZING A 50;59 EVALUATION CONSIDER DESIGN DOCUMENT UPGRADE 1r*

~

. ComEd' DRESDEN STATION Supplier.Evaluation Services E. R. Netzel Supplier E.valuation Services Director I

~ -_. -

ComEd. Audits of AE 'sfocused on:

DRESDEN STATION

  • Design control process with focus on
  • calculations
  • Problem identification & notification

.

  • Interface between ComEd and the vendor

ii

  • ~.

ComEd.

1997AE Audits.*

DRESDEN STATION Bechtel Duke

.Qffsite

  • Site(s)

Off site Site(s)

GE (NSSS).

  • Offsite *.*..
  • Site(s)

.1st Qtr.

  • Complete 3rd Qtr 2nd Qtr 3rd Qtr.

3rd Qtr.

    • 4th Qtr

. Comid DRESDEN STATION Siemens (Fuel)*

Westinghouse _

(NSSS)

Westinghouse (Fuel)..

S.&L t..

1997 AE Audits {Cont.)

Part 1 Part 2 Off site Site(s)

Part 1

.Part 2 CIA_*

-1st Qtr Complete

  • 3rd Qtr 2nd Qtr.
  • 3rd Qtr 2nd Qtr 3rd Qtr 2nd.Qtr Follow-*up* _

-ComEd.

  • . *.Siemens Audit DRESDEN _STATION
  • s*cope: 23 Calculations
  • Reload Specific Calculations* for QC 2C 15 and L2C8
  • Q2C 15 extended operaiing domain/equipment out of
  • Service Cales *
  • Criticality & fuel handling accident c_alcs for Dresden &

LaSalle

  • SUBTIP & LPRM-Out of-Service calcs for DreSden/Quad Cities *.*
  • -Cales associated with Power Plex/MICROBURN _

~ -.

development & testin*g for: LaS_alle Results: No calculational _quality.issues**

I\\~'

,_,_r

ComEd

  • < Bechtel Audit DRESDEN STATION

~,,

.. ~

0 I

r t

.J1 D

Scope:

17 Byron/Braidwood Steam Generator Replacement Project* Calculations

  • 6-Structural
  • I -Mechanical
  • 2-HVAC
  • s~shielding

t*

:'~ *-

ComEd Bechtel Audit (Continued)

DRESDEN STATION Results:.

  • I-Finding I-Unresolved Item Significance*:

6-Level 0 *

  • 8-No Errors 3-Unresolved t

.~)'-~--

0

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