ML20198S727
| ML20198S727 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/22/1998 |
| From: | Schopfer D SARGENT & LUNDY, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-9583-100 NUDOCS 9801260272 | |
| Download: ML20198S727 (32) | |
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Den K. Schoplet Vee President 312 269 6078 January 22,1998 Project No. 9583-100 Docket No. 50-423 Northeast Nuclear Energy Company Millstone Nuclear Power Station, Unit No. 3 Independent Corrective Action Verification Program United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 I have enclosed the following nineteen (19) discrepancy reports (DRs) identified during our review activities for the ICAVP. These DRs are being distributed in accordance with the Communications Protocol, PI MP3-01.
DR No. DR.MP3-0400 DR No. DR-MP3-0783 DR No. DR-MP3-0420 DR No. DR MP3-0842 DR No. DR-MP3-0439 DR No. DR MP3-0879 DR No. DR-MP3 0518 DR No. DR MP3-0913 DR No. DR-MP3-0319 DR No. DR-MP3-0914 b
DR No. DR-MP3-0646 DR No. DP MP3-0918 i I
. DR No. DR-MP3-0675 DR No. DR-MP3-0944 Dr.No. DR MP3-%92 DR No. DR-MP3-0945 DR No. DR-MP3-0775 DR No. DR-MP3-0949 DR No. DR-MP3-0950 l
I have also enclosed the following one (1) DR that has been determined invalid. No action is required from Northeast Utilities for this DR The basis for its invalid determination is included on the document.
DR No; DR-MP3-0972 9901260272 990122 PDR ADOCK 05000423 P
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55 East Monroe Street
- Chicago. iL 60603 5780 USA + 312-269 2000
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United States Nuclear Regulatory Commission January 22,1998
)
Document Control Desk Project No. 9583100 Page 2 Please direct any questions io me at (312) 269-6078.
Yours very truly,
%.T l$'I -
D. K. Se pfer Vice President and ICAVP Manager DKS:spr Encionures Copies:
11 Imbro (1/1) Deputy Director, ICAVP Oversight T. Concannon (1/l) Nuclear Energy Advisory Council J. Fougere (1/1) NU mhvpWwn9ter0122+dne i
t
N<.,theast Uti;.6 es ICAVP DR No. DR MP3-0400 Millstone unM 3 Discrepancy Report Rev6ew Group: system DR VAUD Mov6ew Element: syotem Deegn p
g D6eciplWm: N Doohn
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F ;ry Type: calculeton 4g SystemProcess: sWP
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W Sign 6Acance level: 3 Dele faxed to NU:
Date Published: 1/2596 D6 crepency: Calculation 90-0691065-M3 rev. O contains data the doesn't coincide with the basis document.
D*ecrepuon: Calculation 90-069-1065-M3 rev. O through CCN 06 titled 'MP3 Service Water System NRC Generic Letter 8913, item No. IV Design Basis Summary Report' Several discrepancies were noted as follows:
The introduction section on page 1 states that the model was used to detemined the minimum and maximum available component service water flows. th calculation *, that determine the maximum flow rates have been found or referenced. (Only calculations that determine the minimum flow rates for various scenarios /ete found.)
Table 5 Heat Exchanger Data, should reference calculation 90-0691131 M3, for HVR'ACU1 A/B with a SW outlet temperature of 95 4'F instead of 97.6*F, since the coils for this chiller were replaced.
Page 6 Section ll under Technical Evaluation section states that 1est results were compared to computer model to determine overall model accuracy" yet no computer model document was referenced and no bases was stated for how accuracy was determined or used. It was then stated that "the model wasn1 adjusted to match test data. therefore the accuracy analysis compensates for all contributing factors", but no accuracy baser, or usage was stated. Section Ill.A. Modeling Design inputs and Assumptions, states that "any differences between predicted and tested are accounted for within the calculated model accuracy as described in Section li'. Huwever, it isn1 described in Section 11 as to how the accuracy is accounted for. Any difference between the model and tested data is unclear as to how M will be used or is determined.
CCN #3 updates the minimum required PASS cooler flow without giving justification for doing so. The statement still remains on page 16 that "the analysis to determine minimum
,aquired SW flow to the PASS cooler has not been performed *,
yet an assumed value was listed and now has been updated.
Then CCN #6 updateo.he minimum required PASS cooles flow to the same ar, the miniumum available flow from calculation 97 041, This updated value of 5.1 Opm is less than the flow required during an accident (6.3 gpm), as listed on Table 9.2-1 of the FSAR (dated April 1997).
Review Valid invalid Needed Date tenetor: Dionne. B J 1/1596 Pnnted 1/22/9812.49 36 PM -
Page 1082
Northeast UtHities ICAVP DR No. DR MP34400 Ministone unk 3 Discrepancy Report trut6etor: Diurne B. J.
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VT Leed: Nort, Aremy^
O sitase VT Mgri Schopfer, Don x 0
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Date:
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Date:
MESOLUTION:
Previously idermed try NU7 O Yes ' G i No NonDiscrepentCorwMion?Q Yes 1.9) W Recomt6on Pend 6ng7O vee + No Rosoion nunr wved70 ves @ No Review AccYa* Not Accep.elde Needed Date g,; g VT 1. sed: fjerl, Anthony A 0
0 9
vT Mgri senopter. Don x 0
g m C Chmn: s%n. An.no x Date:
SL Commerde:
I e
Prtnied 1/22.9812 de 43 PM Pe 2 W 2
Northeast Utinties ICAVP DR No. DR MP3 0420 Millstone Unit 3 Discrepancy Report Re,ww oro,: syNo,n DR vAuo Reyww Element: Opereng Procedure Duc6 paine: Mechenced Dewg" O vee D6ecrapency Type: C**
g"g systeWProcese: sWP NRC Signiacence level: 4 Date faxed to NU:
Date Puld6ehed: 1/2d96 Decropency: Incorrect values were used in determining the degraded pump curves for SWS pumps.
Deeceipuun: Calculation NM-022 SWP, rev. O determines the minimum acceptable SW pump curve for ASME XI degredation acceptance. This calculation was reviewed and several discrepencies wers found as follows:
Page S: The calculated minimum required flow includes a measured flow rate to SW Pump lube water which was inmoved from service, Although a calculation change notice should have been written, this flow ls small (3.4 gpm) and can be consideied negligible. The 3 SSP *SCL3 (sample pass cooler) flow rate has been updated per calculation 90-0691065M3 and shouki be changed in this calculation.
Page 9: The SWS Pump 'TDH' was calculated for flows of 6000 and 3600 gpm using an incorrect factor in the equation. A curve fit coefficient of 183.1 was used in place of 182.9 for the determination of both of these values The corred Value was used in calculating the TDH for 10,000 gpm. This errsr does not affect the calculated results.
Review Vei6d invalid M
Date Inteister: Dionne,8 J G
O O
sitsSe VT Lead: Nort, Anthony A g
C O
1/1696 VT Mgt: Schopfer, Don K g
Q Q
1/1&S6 1RC Chmn: Sngh, Anand K Q
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1/21/98 Dae:
18# A U o:
Date:
RESOLUTION Prov6ously identsaed by NUP O vee
'el No Non Discrepent Condition?Q vaJ @ No Resolut6onPendang?O vee + No Renoivuonunresoeved70 vos @ No Review Accepteble Not Accepteblo Needed Date VT Leed: Nort, Anthony A 0
g O
vT Men schopr.r, Don x 1RC Chmn: Singh. Anand K
=
~
Date:
St.Consnente:
Prmied 1/229612.50.23 PM Pepe 1 of 1
Northeast Utilities ICAVP DR No. DR-MP3 4439 Millstone Unit 3 Discrepancy Report Revtow Group: System DR VALID Review Element: Moefceton Desgn 06ec6pline: Mecherwal Deegn O va Diecrepency Type: Instemeten impeemometen tid) No SysterWProcess: SWP
~
NRC Signtacence level: 4 Dele faxed to NU:
Dele Putdeshed: 1/2598 Decropency: Information not fully documented in modification PDCE MP3 140.
Deecription: Modification PDCE MP3-90140, Install Piping Mods to "A" Train SWP at 3HVK* ACUS 1 A. Osveral discrepencies were noted with the documentation supporting this modification. The supporting documents reviewed with this modification included, DCN DM3-P 07190 and DCN DM3-P 060-90.
This modification replaced schedule 10 piping spools with schedule 80 pipe, which reduced the inside Diameter (ID) of the piping. The hydraulic model / calculations should have been revised and referenced in this modification to reflect the 4
reduction in the pipe 10.
DCN DM3-P 07100 which consists of only one page, states that the 'as built dimensions of spool and spacer plate to be attached.
to this DCN", were not included with this DCN. The dimensions of the spool to be replaced could not be verified.
Review Valid inval6d Neded Date inlanator: Denne, B. J.
O C
ii1696 VT Lead: Hert, Anthony A O
O O
iiierse vT Mer: Schope.r Don x 0
0 O
iiio/se IRC Chmn: Singh, Anand K Q
Q Q
1/21/98 Date:
1/15/98 INVALIO:
Date:
RESOLUTION Previously idenoned by NU7 O vee 98 No lion D6screpent Condition?O yee @ No Resolut6on Pend 6ng?O von s) No ResolutionUnresolved70 voa + No Rev6ew Acceptable Not Acceptable Needed Date O
O O
VT Leed: Nwl, Anthony A O
O O
VT Mer: Schopfer, Don K 1RC Chmn: Singh, Anand K Date:
SL Conenents:
Printed 1/22/9612.52.44 PM Page 1 of 1
Northeast Utilities ICAVP DR No. DR MP3 0814 umstorm Unit 3 Discrepancy Report Moview Ofoup: system DRVAUD I
Pctenuel Operetniny leeue D6ecipune: Mecherscal Doog" Om D6ectopency Type: Cok:ulaten (9) No systemWocess: sWP
~
NRC Sign 6scance level: 4 Date faxed to NU:
Date PoJohed: 1/2N98 D6ectopency: Calculations for Reactor Plant CCW Heat Exchanger contained various $1milar errors.
Deocttpe6an: Calculation 94 ENG 1036-M3 rev. O through CCN 02 determines ths Required SW Flow During a LOP Event with a 78'F SW Temperature. Calculation 91 BOP 783ES rev. 2 determines the Required SW Flow Rate to Support a 70.24 Mbtu/hr Safety Grade Cooldown Heat Duty. Calculation 91 BOP 789ES Iev. 2 through CCN 02 determines the Required SW Flow Durir in Safety injection. These calculations contain the fo lowing similar errors:
Equations were not correctly transposed from the reference as follows: Equation 10 noted on page 15 should be noted from page 394 of reference A not page 417 with 110 > 10 not 60, and equation 13 is from page 345 not page 356 Of reference A.
Numerous minor mathematical errors were found throu0hout the calculation. i.e. Pago 20 Tsl for train A and B should be 121.4'F and 120.7'F respectively, based on values listed in calculation,instead of 121.5'F and 120.5'F. Page 24 The values calculated for the prandtl number and film coefficient were not consistent with values calculated based on inputs noted in equations. The overall effect of these mathematical errors can not be determined since the incorrect values are used throughout this calculation.
Data was transposed incorrectly from inputs / equation to equation in various places throughout the calculation. i.e. The mass flow rate (Mt) is listed on page 21 in the results table as 2.34x10E6 (Ibm /hr) and is determined /used in equation on page 29 a2 2.00x10Eb (ibm /hr). Page 38 Thi = 121.5 'F should be 120.5
'F for train B, per page 20. This also applies to Tsi. Page 39 -
The heat duty determined to be 43.5x10E6 on page 13, should have been used instead of 43.54x10E6. Then the heat duty is written and used as 43.64x10E6 on pages 40 and 41, Several typogr:.phical error were noted, The nomenclature ssed for the tube radius (page 7) contains incorrect units. The units should be ft not ft'.
Errors specific to calculation 94 ENG 10:0-TA2 ah, as follows:
Table 2 notes Tso = 95.1*F where design input D states the outlet temperature is 95'F. This is above the maximum allowable value stated in the design input without justification.
CCN 02 removes the reference for 75'F which was incorrectly noted and insert 78'F but does not include a reference or luelinnatinn int muninatinn thlt hant avr harmar at 7A'F The Prtnied 1/229812.Se 20 PM Page 1 or 2
Northeast Utilities ICAVP DR No. DR MP3 0818 Ministow unn 3 Discrepancy Report Tech. Swo. references an UHS temperature of 77'F but does not ado.ess 78'F as IF used in this calculation.
Ermrs specific to calculation 91 BOP 783-ES are as follows:
Page 3 notes re.'erence V as the stress calculation, however this reference is a flow balancing calculation, which is noted consistent with the text of this calculation.
Review Velid invalid Needed Date initiator: Dxmne, 8. J.
O O
O
$'55Se VT Leed. Nort, Anthory A O
O O
t'16's VT Mgra screpler. Doh K O
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IRC ChrtM: Singh, Anand K Q
Q Q
1/21/98 D.:
INVAUD:
Date:
RESOLUTION, Prev 6oJs y hientified try NUr O Yee Si No Non D6ecropont Con (IttonrO vee (e.) No
~
r Resolutton PondinerO vee s) No Resolut6on UnresolvedtO vee (!)No Rev6ew initiator: (none)
VT Lead: Nort, Anthony A VT Mgt: Schopfer, Don K 1R0 Chmn: Sangh, Anand K SL Comnents:
Pnnled 1/129812 se:27 PM Pepe 2 of 2
.- ~ =. -
l DR No. DR MP3 0817 Northeast Utiinies ICAVP Millstone UnN 3 Discrepancy Report Review aroup: cymem DRVAuD Review Element: System Design i
D6scapane: Mechancel Dewe" O, vee Deecrepancy Type: c*w
~ g, sju-?; =*SWP NRCS'f Emlevel: 4 Date faxed to NU:
Date Putdlehed: 1/2 H 6 D6*cr*Pency: Calculations 94 ENG 1037 M3 and 94-ENG-1038-M3 contained various similar errors.
Deecr6puen: Calculation 94 ENG 1037 M3 rev. O determines the required SW flow with a 78'F SW temperature to the Charging Pump Cooit,rs 3CCE*E1 A & B. Calculation 94-ENG 1038-M3 rev. O determines the required SW flow with a 77'F SW temperature to the Safety injection Pump Coolers 3CCl*E1 A & R. These calculations contain the following similar errors:
Data was transposed incorrectly from inputs / equation to equation in varicus places throughout the calculation. i.e. Page 21 -
LMTD is noted in energy transport equation as 47.49'F, however, the LMTD is sis.ted in the result table on page 15 as 47.6g'F. The density of seawater was noted as 64.15 lbm/ft3 at a temperature of 77'F based on reference K. This reference (page 68) refers to a density of 64.00 lbm/ft3 for seawater at 77'F.
The nomenclature used for the tube radius (page 7) contains interrect units. The units should be ft not ft'.
Page 13 refers to reference Z in the calculation as the stress calculation, however this referent e is the Generic Letter 89-13 summary report.
The above noted discrepancies do not greatly impact the conclusions of these calculations. However, calculation 1037 evaluates the service water supplied to the Charging pump coolers at 78'F, calc.1036 evaluates the reactor component cooling water heat exchangers at 78'F, and calc.1038 evnluates the safety injection pump coolers at 77'F. There doesn't seem to be a consistent evaluation of the SWS components at elevated SW inlet temperatures. The Technical Specification refers to an UHS temperature up to 77'F but does not address 78'F as used in calculations 1036 and 1037.
Rev6ew Velid involod Needed Dele init6etor: Donne. B. J.
Q O
Q 1/1%6 VT Leed: Nort, Anthony A Q
Q Q
1/16/96 VT Mge: Schopfer, Don K O
O O
ilias6 IRC cisnn: Singh, Anand K Q
Q Q
_1/21/96 Date:
INVAUD:
Dele:
nesOLUTION:
Printed 1/229612.s7.04 PN Page 1 of 2
Northeast Utilities ICAVP DR No. DR-MP34519 Miliston Unit 3 Discrepancy Report Prov4ouefy beenciled try NU7 U Yee e) No Non thecropont Constion?U Yes
- 9) No Reec%stionPoneng?O Yes
- 6) No Ree.iui6anvaree wdrO vee E) N.
Rev6ew Acceptable Not Acceptable useded Date gg,g,;
VT Lead: Nort. Anthony A VT Mgr Schopfer. Don K 1RC Chmn: Sngh, Anand K O
O Dese:
SL Comnenta:
l s
Prned 1/22.981257;10 PM Page 2 of 2
I Northeast Utilities ICAVP DR No. DR MP3 0W Millstone Unit 3 Discrepancy Report Revtew oroup: System DR VALIO Peterdial Opereldisty leeue Dioc6pline: Mechencel Doogn O va D6screpancy Type: Calcunston
'e) No SystemProceae: DGX NRC Signeacance levet: 4 Date FAKod to NU:
Date Published: $/2s96 i
D6screpency: Discrepancies for Calculation P(T)-0997 Deecript6on: Reviewing the calculation Emergency D asel Generator (EGS)
Operating Conditions (for SDP)", calc. no. P(T)-0997 Rev. O, following discrepancies were noted:
- 1. Objective of IMs calculction is to " determine the operating conditions for the Stone & Webster supplied cooling water lines to the Emergency Diesel Generator (Jacket Water and Intercooler Water Systems) for the Stress Data Package". The list of considered piping does not fully match the lines as listed on the EGS Line List and as shown on the system PalD's (EM.
116A 27 and EM 116C-12), and as needed to support the Stress Data Package. The calculation does not triclude lines with the sequential line numbers 17 through 26,
- 2. Calculatiot; Operating Condition 3 postulates a failure of an Air Operated Valve 3EGS*AOV43A/B in the full bypass modo during a maintenance run (page 6 of the Calculation). This valve is not on the system P&lD. It could not be found in PDDS database either. Valves 3EGS*AOV43A/B appear to have been replaced by valver. 3EGS*TCV50A/B.
Review Valid invalid Needed Date init6ator: Obersnel,Bolen O
O O
sii&se VT Leed: Nort. Anthony A G
O O
tSS8 VT Mgt: Schopfer. Don K Q
Q Q
1/1998 1RC Chmn: singh, Anand K O
O O
tr2irse Deio:
INVALID:
Dele:
RI!aOLUTioN:
Previously identined by Nu? O Yes
- 1 No Non D6ecrepent Comisuon?O vos @ No ' '
Resolution Ponding70 ves + No ResosutionunresoivedtO vee
- 3) No Review Acc*Ptable Not Acceptable Needed Date g,gg g VT Lead: Nort, Anthony A VT Mgr: Schopfer. Don K IRC Civ. n: singh. Anand K Dele:
SL Commente:
Prtnted 1/22,9812.57:55 f%4 Page 1 of 1
i Northeast Utilities ICAVP DR No. DR MP34675 ministone unit 3 Discrepancy Report Megtow Group: System DR VAUD Potent 6el Operetnity leeue O vee Dioctopency Type: Coculaten jg system 9tocese: DGX
~
NRC signeacance level: 3 Dete faxed to W:
Dele Putd6eheI: if259e 06*ctopencyf Discrepancies for Calculat!on SDP EGS-01345M3, Rev. 05 D cripe6en: Review of the calculation ' Emergency Diesel Jacket Water and intercooler Water (EGS) SDP' (Stress Data Package), calc. no.
SDP EGS-01345M3, Rev. 05 rescited in the following discrepances:
- 1. Operating Condition 3 assumes that the valve 3EGS*AOV43A/B falls in the full bypass mode. Valve 3EGS*AOV43A/B is not shown on the EGS system P&lD's EM.
116A 27 and EM 116C 12, and it could not be found in the PDDS data base. Valves 3EGS*AOV43A/B appear to have been replaced by valves 3EGS*TCV50A/B. (This discrepancy was also noted in a reference to this calculation, calculation P(T)-
0997, as documented in the Discrepancy Report # DR MP3 0646.) Valve number 3EGS*AOV43A/B 15 also listed on the Miscellaneous information Sheet, Section e., page 19 of the calculation.
- 2. The table System Design Conditions, page 14 of the calculation was apparently constructed using the Line Designation Table (Reference 1). However, unlike the System Design Conditions table, the Millstone lli Line Report of 8/12/97 has no entry for design pressure for piping from the fresn water expansion tank to plant drainage, and piping from 3EGS*RV32A/B drain funnel to the floor drains. No supporting justification, either directly or by reference, w3s found in the calculation !or this design pressure.
- 3. Line no. 3-EGS 500 26 3 in the SyMem Design Specification Sheet (page 15) is not shown on the system P&lD. Line List entry for the location of the line indicates that the line runs from the Diesel Generator A (3EGS'EG A) to the hose 3EGS* HOSE 6 B on the Diesel Generator B, which is not supported by f ne P&lD.
- 4. No justification or refarence is provided for the number of cycles for operating conditions (pages 11 and 12).
- 5. Calculation Attachment 1 provides flexible hose information.
On page 2 of this Attachment Young's modulus for the 0.5 in.
hose is calculated; execution of the given numerical equation does not yield shown result (1352 vs. 2120). The equation could not be reproduced because of lack of supporting information (assumptions, references / sources, units) for selected equation and its parameters. This apparent error was then propagated in the ensuing calculation cf shearing modulus. Also, Page 1 of this Attachment refers to Ref a (for hose stiffness) and Ref. b (for he weight); n:Mr of 'M: r:f:r== !c p cWgg p
,gg
Northeast Oulities ICAVP DR No. DR44P3 Ot75 Misistone unn 3 Discrepancy Re, ort in the Attachment or the main body of the calculation. Further, the Attachment refers to data obtained from Aeroquip. However, no supporting document is either encio:*1 or referenced.
Rev6 w Vand invahd Needed Date inmastor: ote snet.s * -
O O
O ir a9e VT Leed: Nort, Arceny A O
O sita9e VT Mgr: Schopler, Don K Q
Q Q
1/1a96 IRC Chmn: Singh, Anend K Q
Q Q
1/23.9 6 Dele:
IIWAUD:
Dele:
RESOLUTION:
Prev 60uely identsfled by Nu? O Yee
() No Non D6ecropont Condition?O Yes (4/ No Resolut6on Pend 6ng?O.~..
si No Recoiuisonurwoeoev.drO Y.e i No Rev6ew Acceptable Not Acceptable Needed Date VT Leed: Nort, Aremny A VT Mgr: Schopfer, Don K IRC Chmn: Singh, Anand K a
Dese:
SL Commente:
Printed t/22/9e i2.50 46 PM Page 2 of 2
Northeast Utilities ICAVP DR No. DR MP3 0492 Ministone unit 3 Discrepancy Report Rev6ew Group: Syelem DR VAUD Review Element: Syelem Deegn D6ecepline: Mechencel Deegn O Yeo r"==7.:y Type: Calculeton
@) No systemProcese: DGX
~
NRC s6pnescence level: 3 Date faxed to NU:
Date Putd6ehed: 1/2596 D6ecrepeacr: Discrep6ncies in Calculation SDP-EGA 01342M3, Rev.02 Deecript6on: Reviewing the calculation " Emergency Generator Air (EGA)
Stress Data Package", calc. no. SDP EGA-01342M3, Rev. 02 following discrepancies were noticed:
- 1. Operating Condition 3 postulates inadvertent closing of the excess flow valves 3EGA'V983 through *V986 (page 11). This is not in agreement with the calculation no. P(T) 1042, Rev. O, which is referenced (Ref. 3a) in the subject calculation.
C inculation P(T) 1042 assumes that the isolation Valves 3EGA*V995, 'V994, *V982 and 'V981 are inadvertently closed for this operating condition.
- 2. Operating Condition no. 5 postulates that the air receiver tank relief valve (3EGA*RV24A1,A2.B1,B2) fails open. This mechanical failure is different from the failure postulated in the referenced calculation P(T) 1042, where the air compressor relief valve (3EGA RV20A1 A2.B1,B2)is postulated failed open.
Postulated failure of the air receiver relief valve will keep the air compressor running supplM air receiver tank with the air above ambient temperature The System Design Specification Sheet (page 15 of the calculation) shows the temperatures for the Operatir'g Condition 5 to be ambient (AMB) throughout the system.
- 3. No justificatien is provided for the number of cycles for Operating Conditions.
Review Valid inve46d Needed Date ine 6etor: Obersnel.Botan.
O O
O 1 '***
VT Leed: Nort. Anthony A Q
]
]
1/&96 VT Mer: Schopfer. Don K
]
Q 1/199e IRC Chmn: shgh, Anand K O
O O
1r2iise Deie:
INVAUO:
Date:
RESOLUTION:
Prev 6ously identeRed Ipy Nuf Q Yee ? No Non Discrepent Condluon?O Yes 41 No Resolution Pend 6ngtO vee + No ReeceutionUntosolvedrO vee 4) No Review Acceptable Not Acceptable Needed Date VT Lead: Nern. Anthony A VT Mgr: schopfer. Don K PrWed 1122/9612.Se 43 PM Pege 1 of 2
]
Northeast Utilities ICAVP DR No. DR MP3 0492 Millstone unN 3 Discrepancy Report 9
g mc ch n: sne, An.no x 0
0 Dele:
SL Comments:
s 2
PrHed if229012 SS 48 PM Page 2 of 2
4Wi Nottheest Utilities 10AVP DR No. DR MP34775 Millstone Unit 3 Discrepancy Report Rev6ew Group: Ps.vyemmetc DR VALM Rtview Elemort: Change Process Dier W e Mechancel Design y
r" n, my Type: Dwgn Cortroi Proccours pg SystemProcess: RsS
~
NRC Signincance leve1: 4 Date FMed to NU:
c Dede Putdished? 1/2sf96 Diecrepeacy Modification Packages not Consistent with Design Control Manual Requirements Deecriptica A review of modificatico packages has identified the following cases where the documentation is not consistent with the requirements of the Declgn Control Manual.
E DCR g70610 This modification package does not comply with Chapter 3, attachment 3 3, of the Design Control Manual. That is, there is no Table of Contents which lists the total design package contents. Nor are there enclosures which are required
=
to contain/ identify supporting design information.
SCR 975800This modification package includes a Table of Contents (TOC) which does not comply with Attachment 3-3 of the Design Control Manual. Attachment S-3 is very sp6cific as to the content and organization of the TOC. The TOC in the
[
.nodihcation package identifies some of the forms frorr *~
g Manual but is not consistent. For example, there is n
'c:
B which should be a
- List of Affecte( Wuments ar Document Markups.' Attachment *
- ates, "Eact
+t should have an index and be pagm 8 d in sequenc4.
a enclosure is not needed, it should be so identified on the table of contenis with no enclosure index reqa! red.'
Review g
Valid invalid Nc6ded Date t
Initiator: Wnma s P.
G O
O
'It S/S8 VT Lead: Ryan. Thomes J G
O O
1'1SS8 VT Mp: schopfer. Don K E
O O
S'S8 BRC Chmn: singh. Anend K Q
O O
1/21/98 Date:
INVALio:
Date:
RESOLUTION Previously identified by NU? O Yos E No Non Discrepent Condition?Q Yes (#1 No L
Reec'ution Pending?O ve. + r.
Resosution unre.oivea?O Yes @ No Review
, Acceptable W Accepta5le N,eded Date VT Lead: Ryan Thomas J VT Mgr: Schopfo, Don K IRC Chmn: singh ?m..d K Date:
SL Comnums:
Pnnted 1/22,961:0o:47 PM Pega 1 of 1
Northeast Utilkies ICAV."
DR No. DR MP3 4783 Millstone unk 3 Discrepancy Report Review Otoup: Opershone & Mordenence and Testing DRVAUD-Peview Element: Correc#ve Action Process Diecipline: Operatene Ow r"--
y Type: Correcove Acton g
SyJtemProcese: Rss NRC Signiacance level: 4 Date faxed to NU:
Date Putillahed: 1/25/9e Dier.repancy: Licensee Event Report (LER) Root Cause Determination inadequacies /Close-out inadequacies
==
Description:==
Millstone Unit 3 LER 89-017-00 was written to identify an event where one of the motor-operated containment isolation valves (3RSS*MOV200) for the Containment Recirculation Spray header had not been fully operable for 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> and the required 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Technical Specification action had not been performed.
The LER concluded that the root c&use of the event was inadequaite admin;strative guidance on the definition of corOlnment isolation valves, which led to a misinterpretation of the Technical Specifications and the FSAR on the part of the operators and the operations shift management. The LER commited to include guidance on containtnent isolation valves in permanent plant procedures by February 28,1990.
Commitment Record No.17558 was initiated to resolve and track this item. The commitment states: 'As action to prevent recurrence, inteiim guidance was provided indicating C 9alves listed in FSAR Table 6.2-65 are containment isoiauon valves. Finai guidanco will be included in permaner't plant procedures by February 23,1990." The Validation 1 axt states, c
however, that t*ie final guidance is already containt i in the Technical Requirement,, Manual, STRM 3.6.3.
Additios' ally, two more commitments were made to resolve the LER con mitment. They were:
(1) Commitment No. 3-89 0192, which stated: " Provide clarification to FSAR Table 6.2-65 to definc clearty which valves are containment isolation valves for purposes of T.S. 3.6.3.' The only action taken was addition of a note which states: " Changes to this table require.10CFR50.59 evaluation in accordance with Technical Specifis.ation 3/4.6.3 bases." The item was closed wt;hout providing clarificat!on or guidance.
5 (2) Commitment No. 3-89-0151, which stated: *% 1neering to revise / develop a new FSAR Table-6 showing cc.aalnment penetration, required accident state & leakage requirement (relative to air / water and bypass leakage)." FSAR Table 6.2-65 already conttilned these items, and no enance wrss tr&'a.
v Since all of the commitments made in LER 89-017-00 failed to result in revisions to administrat!ve guidelines to correctly identify conta;nment isolation valves Northeast Utilities (NU) should hava revised the root cause detennination in the LER.
Review Printed if22/9e 121:34 PM Pege 1 of 2 l
m i
Northeast Utilities -
ICAVP DR No. DR MP3 0783 Millstone unk 3 Discrepancy Report VeM kiveM Needed Dele kdtietor: Pecooky,Al.
g 12/22,97 VT Leed: Beee, Ku. _
Q Q
12/2497 o
VT Mgr: Schopfer, Don K -
Q 1/1996 IRC Chmn: Singh, Anand K Q
Q 1/21/96 Dele:
INVAUD:
Date:
RESOLUTION:
M/:r'y identitud by NU7 O vee fe) No Non N:.- "Condelion?Q vos @ No PM% Pending70 vee @ No aseosuiionune oived70 vos @ No Review Mietor: (none) 9 V' Lead: Beee, Ken VT Mgr: Schopfer. Don K l
lRC Chmn: S@, Anand K O
Date:
SL Conenents:
3 z.
i e
i'rwed 1/225161:01:40 PM Page 2 of 2
Northeast Utilities ICAVP DR NJ. DR4AP34V2
- Millstone Unit 3 Discrepancy Report Review oroup: S)m DR VALID Review Elemer:t: Syelem Design g
Diecipline: Structurel Design O v.
D6ecrepency Type: Calculation gg g SysteWProcess: HVX NRC Signanconce led: 4 Date faxed to NU:
Date Putdlehed 1/25/9e D6ecrepency: Duct Support Calculation Discrepancy De*crir*. ion: We have reviewed Equipment Support Calculation no.12179-NP(F)-Z545J 1288,Rev.2.
Based upon this review,we have noted the following
]
discrepancies:
- 1. On pages no.14 & 15,the following input errors have been identified; a) Z coordinate at joint no. 59 should be '-18.0' (not + 18.0).
b) Two different BETA angles ( 0.0 and 180.0) have been defined for the same member
( member # 27 )
c) BETA angle has not been defined for member # 33.
~
- 2. Flare Bevel Weld check has not been considered at jt.#
35,38,44,47,33,41,42 & SO (See calc. pages no. 20 & 22).
Review Valid invalid Needed Date init6stor: Kleec. N O
O O
1/1SS8 VT Leed: Nort, Anthony A y
Q Q
1/1ESe VT Mgr: Schopfer. Don K G
O O
irisse IRC Chmn: Singh. Arend K G
O O
1'21/S8 Dois:
INVALID:
Date:
RESOLUTION Previously identeAed by Nu? O vos f No Non Discrepent Condition?O vee @ No Reeoiution Pendeng?O vee tv No Resoeunionunroeoived?O vee @ No Review Acceptable Not Acceptable Needed Date gg VT I wd: Neri, Anthony A VT Mgr: Schopfer. Don K IRC Chmn: Singh Anenct K Dele:
SL Comments:
' Prtreed 1/22.11e %:04 U PM Page 1 of 1
{
l
~
i Northeas Utilities ICAVP DR No. DR MP3 0419 Millstone Unit 3 Discrepancy Report Review oroup: sycom DR VAuD Poview Element: System Des %n p
Diecipline: Mechancel Desgn gy Cer ;- ;y Type: Conculeton g
8,
T.--- = s W P NRC Spen e level: 3 D* faxed to NU:
Date Putd6ehed, if2sS6 D6screpancy: Seistnic reports are not available for ICAVP review for the j
following equipments.
Descripuon* (1) 3EGS* HOSE 1 A/2N2B/3N3B/4N48. Seismic report requested per RFl#756. Item #5, Qualification report provided( No. 206072 ) did not qualify the hoses.
(2) 3EGS*LS34A/B. Seismic report requested per RFl#669, item #40, Response IRF#1098 said that this item is get,srically qualified as a part of diesel generator equipment.
Qualification report No. 206072 does noi address these level switches.
(3) 3EGF*PS38'JB Seismic report requested per RFl#689, item #46. NU Response in IRF#1098 said that these equipments are generically qualified as a part of diesul generator equipment. Report No.206072 does not address the qualification of these pressure switches.
e (4) 3 EGO *PS23A1/A2/A3/B1/B2/83. Selsmic report requested per RFl#669, item #47. NU Response in IRF#1098 said that these equipments are generically qualified as a part of diesel generator equipment.
Report No.20607' does not address the qualification of these pressure 1-es.
(5) 3 EGO *TS30NB. Seismic report requested per RFl#670, item #9. NU Response in IRF#903 said that there is no spacific seismic qualification exists for these equipments.
These equipments are on the skid mounted piping and are generically qualified by vendor. Report No.206072 does not address the qualification of these tem e: 4ture switches.
Review Valid invalid Needed Date init6ator: Petet, Ramesh 8
O
-O isse VT Lead: Neft, Anthony A O
O O
iSS8 VT Mgt: schopfer, Don K O
O O
1/1SS8 E
IRC Chmn: singh. Anand K Q
Q 1/21/96 Date:
INVAUD:
Date:
RESOLUTEN Previously identleed by NU? O Yes le) No Non D6screpent Condition?O Yes @ No Pnnled 1/22/9e 1:06:06 PM Pcge 1 of 2
l Northeast Utilities ICAVP DR No. DR MP34879 maistone unit 3 Discrepancy Report Pad % Pendeng?U Yes @ No PMdion Unresolved?Q Yes @ No Review A=
- ^2 "; Not '- -- - * '
Needed Date VT Leed: Nort, Anthony A VT Mgr: Schopler, Don K 1RC Cisnn: Singh, Ansed K O
O O
Date:
SL Comments:
t e
1 4
9 Printed ifD961:05:13 PM Page 2 of 2
I Northeast Utilities ICAVI.
DR No. DR MP3 0913 Milistone Unit 3 Discrepancy Report Revtow Group: Pror/emmetc DR VAUD Review Element: Correctrve Acton Process Diecipline: Other Ow h
ai Type: Correctrve Acton gg SyelemProcese: SWP NRC Signiacance levet: 3 Date faxed to NU:
Dele Pub'4ehed: if2MI6 D6ecrepancy: Inadequate 10CFR50.59 Safety Evaluations
==
Description:==
ACR M3-96-0357 dated 7/8/96 is associated with LEtt 96-005-000. The ACR states that nelther the Bypass Jumper evaluation by the Engineer, Supervisor, and Plant Review Committee, nor the 10CFR50.59 evaluation addressed the deletion of the high temperature auto-start function of the Service Water System booster pumps. The corrective action states that the procedures for safety evalJallons have been 'sighlficantly strengthened.'
Also,
- A standard form is now used for all safety evaluations, and there is a dedicated subcommittee of the Nuclear safety Assessment Board that reviews all safety evaluations....'
Although this recognizes that performing safety evaluations is a problem, the corrective action only addresses future safety evaluatlods through a revised procedure and a subcommittee. It does not address the extent of the condition, ACR M3-96-0041 identifies an inadequate 10CFR50.59 safety evaluation with respect to a PDCR involving the Service Water 2
pump dscharge valves. The corrective action plan included in the *.CR is inadequate in that no action is addressed relative to the inadequate safety evaluations.
ACR M3-SS-0920 identifies two inadequate 10CFR50.59 safety evaluations, for which no corrective action was established..
UIR-2458 identified where a safety evaluation was not performed
?~
when the setpoint of a level switch for the Refueling Water Storage tank was changed. This setpoint changed the approved levels as shown in the FSAR. The final disposition was to perform a 10CFR50.59 evaluation to assure that the change did not result in an unreviewcd safety question. This was the appropriate immediate action to take to resolve the immediate deficiency; however, the cause of the problem was not addressed. That is, the reason for a safety evaluation not being performed, was not addressed The above are indicative of a possible generic problem associated with the failure to perform required safety evaluations, and the adequacy of those evaluations ti:st are peiformed. Since ihere are a number of situailons where in:acequatEi SDNt) evaluations have been performed, the extent of the condition needs to t,e evaluated. Additionally, the corrective actions which have been taken do not address such items as the qualifications and training of the individuals performing the evaluations.
saview Valid invalid Needed Date
"" Wmna CD iMC Prtnted 1/22/961:05.56 PM Pege 1 of 2 i
l Northeast Utilities-ICAVP DR No. DR MP3-0913 Millstone unit 3 Discrepancy Report insuetor. Wrone,6. P.
Q Q
Q 1/15W6 VT Leed: Ryan, Thomoe J Q
1/SV96 VT Mgr: Schopfer, Don K Q
Q 1/2098 IRC Chmn: Singh, Anand K Q
Q Q
1/21/96 Date:
l' WALID:
Date:
RESOLUTION.
Prev 6ously hientdted by NU7 O Yee (9) No Non D6ecrepent Condition?O Y.4 (e) No Resolution Pend 6ng70 vee r*) No Reconution unt 4,.470 vos @ No Moview initletor: (none)
VT Lead: Ryan, ThoTwo J VT Wgt: Schopfer, Don K 19C Chmn: Srgh. Anand K SL Comments:
k a
Prtnted 1/22/96196.02 PM Page 2of 2
__.-_________.__-m_
i Northeast Utilities ICAVP DR No. DR MP3-0914 -
Milistone unit 3 -
Discrepancy Report i
Review Group: Programmatic DR VAUD Rev6ew Element: Correceve Action Process p
Diecipl6ne: MecherWcel Des
- O Ya Discrepancy Type: Correctrve Acbon 4g Syelemstocess: R$s
~
NRC Sign 6Acence level: 3 Date faxed to NU:
Date Published.1/25/96 D6ecrepency: IncorTect ACR Closure Deecrtpt6on: ACR # 10773 contains the following which are indi:.ative of improper closure.
- 1. The ACR was separontly changed to a Significance L.evel B (from D) on the Adverse Condition Report Transmittal Sheet, and a reportability determination is required. There is no Reportability Determination included in the package.
Additionally, this incident appears to have been reportable under 10CFR50.72 (2) (1) which states, Any event, found while the reactor is shut down, that, had it been found while the reactor was in operation, would have resulted in the nuclear power plant, including its principal safety barriers, being......in an unanalyzed condition....' is reportable.
- 2. This ACR was apparently clored without PORC review. A note incitocd in the package states that the ACR was taken to PORC four times without success. The response to the note is to *Close the ACR without PORC review.' No justification is provided with the remark. Another note is included on the Casual Factors and Corrective Action Plan stating 'ACR may be closed without root cause or PORC review", again without explanation or justification.
Review Valid invalid Needed Date initiator: Wrone. S. P O
O O
v88 VT Leed: Ryan. Thomas J B
O O
1'S5'8 VT Mgr: schopfer. Don K O
O O
1'1S'88 IRc Chmn: Siryh, Anand K O
O O
1r2ii9e Date:
INVAUO:
Date:
RESOLUT*ON:
Previously ident6fted by NU? O Yes 95 No Non Discrapent Condition?O Yes t#) No Resolution Pecdong?O Yes I No asolutionUnresolved70 Yes @ No Review Acceptable Not Acceptable Needed Date VT Lead: Ryan, Thomas J VT Mgt: Schopfer. Dor: K IRC Chmn: s6ngh, Anand K Dele:
SL CommerWe:
Printed 1/22/961:o6'43 PM Page 1 of 1
l l
Northe.ast Utilities-ICAVP DR No. DR MP3 0918 Millstone Unit 3 Discrepancy Report Rev6ew oreup: syenem DR vAuD Revisw Element: system Deegn p
O vee Diecrepency Type: Drew 6n0 gg systemProcoes: DGX
~
NRC signiacence level: 4 Date faxed to NU:
Date Pulsehed: 1/2 A' e D6ecrepency; Discrepancies on EGA System Isometrics Ducrisdion: Reviewing system isometrics for piping as built dat.a the following discrepancies were noted:
- 1. Line no. 3-EGA 500-64 2, as shown on the P&lD EM-1168-25 and as described in the Line List, is on the isometric CP 360258 Sh.1 of 4, Issue 6 erroneously shown as line no. 3-EGA 500 3. It is noted that the line number 3-EGA 500-61-3 is also used for a line in the starting air train 2B, shown on the P&lD EM-116D-5, and on the isometric drawing CP-360257, Sh.1 of 3 j
issue 4.
- 2. Piping represented on the P&lO EM-116B 25 by the line numbers 3-EGA 500-90-3 and 3-EGA 500-913 is not so identified on the isometric drawing CP-380258, Sh.1 of 4, issue
- 6. The Line List shows no entry for a reference isometric drawing for these lines.
- 3. Piping represented on the P&lD EM-116B-25 by the line numbers 3-EGA 500-85 3 and 3-EGA 500-89 3 is not so e
identified on the isometric drawing CP 360259, Sh.1 of 4, issue
- 5. The Line List shows Po entry for a reference isorretric drawing for these lines.
- 4. Piping represented on the P&lD EM 118.i-5 by the line numbers 3-EGA 500-86-3 and 3-EGA %0-87 3 is not so iderCfled on the isometric drawing CP-360-260, Sh.1 of 4, Isste S. (The drawing is identified by the drawing number CP 360-260 on sheets 1 and 2, and by the drawing number CP 360260 on sheets 3 and 4.) The Line List siiows no entry for a reference isometric drawing for these lines.
Review venid inve:L.
Needed Date snaietor: otwronei.Boien-O O
O 52r27/97 VT Lud: Nwt Anthony A B
O O
1/5/se VT Mge: Schopfer, Don K Q
Q O
1/19/96 IRC Chmn: sin 0h. Anend K O
O O
t/21/98 Date:
INVAUD:
Date:
RESOLUTION:
Previously identtaed by NU7. Q Yes @ No NonDiscrepentConddion?O Yes @ No R.e.wion esamnetO Y=
@ No RuoMionunresolved?O Ya @ No Rawlew Prtnied 1/22/981;o6:32 PM PeGe 1 or 2
Northeast Utilities ICAVP DR Nc. DR-MP3 0918 Millstone Unit 3 Discrepancy Report a ce.pe.m Not Acceptande Needed Date VT Lead: Nort, Anthony A VT Mgr: Schopfer, Don K RC Chmn: Srigh, Anand K O
O Dele:
SL Comnents:
o 8
t
^
a 4.
+
Printed 1/229S 1:0026 PM Page 2 of 2 l
)6 l
l 1
s l
Northeast Utilities ICAVP DR No. DR-f2P3-0944 Millstone unit 3 Discrepancy Report Rev6ew Group: Operations & Martenance and Testing DR VALID Rev6ew E'.anent: Conectus Action Procese p
Diecipline: Operation.
Ow D6ecrepency Type: conectue Action gg Sy temProcess: DGY NRC Sigh. level: 4 page FAN to NU:
Date Published: 1/25/9e D6ecrepancy: Procedure revisions de not prevent recurrance of event reported in LER 89-015-00 Deoxiption: A review of the requirement described in REQ-MP3-DGX-0289 was unable to determine t w the corrective actions prevent the operating error described in LER 89-115-00 from recurring under simllar circumstances. LER 89-015-L't reports a failure to assure that the "A" Emergency Diesel Generam and its associated "A" Train 4180/480 VAC Emergency Busses were fully operational prior to removing the "B" Emergency Diesel Generator from service. This is a discrepancy.
OP Form 3672.12 is performed daily but only confirms that the bus is energized. There is no provision for the operator to record the bus ic3d or to compare it against a limiting value based on the power source. Therefore, OP Form 3672.1-2 would not prevent recurrence.
OP 3344A describes the necessary steps to manipulate the power source to the 480v load centers with precautions but there is nothing that In'orms subsequent shifts that there is an unusual eteencal line-up that limits the load carrying capabilities of the bus. Therefore, the operator does not have the necessary information available to rnake the correct decision regarding operability issues of the oppo',ite emergency diesel generator.
Therefore, OP 3344A would not prevent recurrence.
This procedure also requires removing the A " CAR" Fan from service it bus 32S is being supplied through a cross-tie.
However, the portion of OP 3344A that retums bus 32S to its normal supply does not mention reluming the A " CAR" Fan to an operational condition.
Commitment Record 17554 commits to " Issue a new procedure to deilneate the Electrical Plant Lirie-up condit!ons..." The review was unable to determine from the Validatiori Text what new procedure was issued. lastead, it appears that an existing procedure was revised.
Review Valid Invalid Needed Date initietor: Tamtyn. Tom O
O O
1/18S8 VT Lead: Base, Kan 8
0 0
'itte 4>
VT Mgt: Sctmpfer, Don K Q
Q 1120/98 talc Chmn: Singh, Anand K.
O O
O 1i21/9e Date:
INVAUD:
Printed 1/22/9e 1:o0:14 PM -
Pope 1 of 2
Northeast Utilities ICAVP DR No. DR MP3 0944 Miiistone unk 3 Discrepancy Report Deie:
RESOLLm 0N Previously klontened by NU7 O Yes
'V) No Non D6ecropont Condson?O Yes
- 9) No Reso6utionPoneng70 Yes + No nosoivisonunrevedtO Yes @) No Resiew Acceptable Not h@ Needed Dele g,,
VT Laod; Be4 Ke..
VT Mgr; Schopfer, Don K 1RC Chmn: San 0h, Anand K
=
Dete:
SL Commoots:
s PrWed 1/22S61:09:20 PL:
Page 2 of 2
Northeast Utilities ICAVP DR No. DR-MP3-0948 milistone Unit 3 Discrepancy Report Review Group: Operstmo & Mi.Wenance and Testing DR VALID Review Element: Corrective Acta Procesa Diecipline: Operet e O va Diecrepexy Type: Correctfve Actm 'snplerneraste
@ No System / Process: DGX NRC Signinconce level: 4 Date faxed to NU:
Date Putdinhed: 1/2596 D6ecropency: A commitment to instruct operators to open D/G exhaust hatch in case of ice buildup has been deleted
==
Description:==
In a letter to the NRC dated 5/17/84, the station committed to provide in5tructions to station personnel that in the event of ice build-up on the diesel generator exhaust access hatch or a tomado alert that the hatches should be opened. A precaution existed in OP 3346A to aodress this issue.
Revision 19 of OP 3346A remond this precaution based on memo MP3-DE 950863 (PLAAR 3-94-4), Memo MP3-DE-950863, dated 7/17/95 was written to remove the requirement to open the access hatches in the event of a tomado alert. The memo does not address the elimination of the requirement to open the access hatches due to the build-up of ice, Since the precaution that was deleted in OP 3346A addressed both ice build-up and a tomado alert, this is o discrepancy.
DR No. DR MP3-0949 addresses a similar problem.
Review Valid lovelid heeded Date initletor: TerrWyn Tom G
O O
1/s/s.3 VT Leed: Bass, Ken Q
Q 1/5V96 VT Mgt: Schopfer, Don K O
O O
tristo6 IRC Chmn: singh, Anand K Q
Q Q
1/21/98 Defe:
G A, ALIO:
Date:
RESOUITION:
Previonely identified by NU7 O ves @ No Non Discrepent Conddion?O Yes @ No Heeolution Pendmg?O vec @ e.4 Recoiuiion unresoeved70 von @ No Review Acceptable Not AcceptetA. Needed Date gg VT Lead: Bees. Men VT Mgt: Sewpfer Don K IRC Chrun: cingh, Anand K Date:
SL Commente:
Printed 1/22,961:0957 PM -
Pege 1 of 1
Northeast Utilities ICAVP DR No. DR-MP3-0949 Millstone un't 3 Discrepancy Report Rev6ew Group: Openec.w a Maritonarce and Testing DR VAUD Review Element: Correctwo Acoon Process D6ecipione: Operations O va D6ecrepency Type: Correctue Action trnpiementation 4'-
4 Systemfrocese: DGX NRC Signiecence Imt: 4 Date faxed to NU:
D=8e Published.1/25S6 Decr*Pev No AOP that requires inpection of D/G exhaust hatch if as t olential for ice buildup exists Descripuon: In various communications between the applicant and the NRC resulted in a commitment by the applicant that they would include in an abnormal operating procedure the requirement to periodically inspect the diesel generator exhaust hatch in the event of an ice storm, snow storm or freezing rain to ensure the hatch remains operable.
The review could not identify any abnormal operating procedure that would satisfy this requirement. There is an abnormal operatiiig procedure for severe weather Conditions, AOP 3569, but it only addresses tomado or hu Ticane conditions.
Review Van 6d invalid Needed Date initiator: Tenvyn, Tom O
O O
1/8S8 O
[
1/946 VT bud: Bass, Ken VT Mge: schopfer, Ocn K Q
[
1/19S6 IRC Chmn: swigh, Anand K g
Q Q
1/.71/98 Date:
INVAWO:
Sete:
RESOLUTION:
Previously idenH8ed by NU? O vos ei No Non 0;screpent Conddior.?U ves it) No Reso4ution Pending?O ve.
J) No Reso6ution Unresolved?O ve.
@ No Review Acceptable Not Acceptable Needed Date VT Lead: Bass, Ken VT Mgr: schopfer Don K IRC Chmn: Singh, Anand K SL Comnents:
1 1
Printed if22S61:10'43 PM Page 1 of 1 1
L Northeast Utilities ICAVP OR No. DR-MP3-0960 Ministone Unit 3 Discrepancy Report Rev6ew Group: system DR VALIO Review Element: System Design p
D6ectpoine: Mecherwcel Design O va 06ecrepency Type: Componers Data Is) No SystemProcess: DGX
~
NRC Signmcence level: 4 Date faxed lo NU:
Date Published: 1596 D6ecrepency: Maximum Operating Conditions for Emergency Diesel Generator Fuel Oil System Deecr6puon. The FSAR Tab,e d.da. " Moderate Energy Systems Outside Containment Remote from Essential Systems, Components, and Structures" states that the maximum operating Conditions for the Emergency Generator Fuel system are 40 degrees F and 29 psig. Per calculation SDP EGF-01344M3, Rev. 3 " Emergency Generator Fuel Oil (EGF) Stress Data Package", the maximum operating conditions for this system are 31.5 psig and ambient temperature. The system is exposed to three amb!ents with maximum temperature no less than 90 degrees F, and as high as 120 degrees F.
Review Valid Invalid Needed Date Ininetor: Obersne4,Bojan-G O
i 4s8 VT Lead: Nort, Anthony A G
O 5'1'S8 VT Mgr: Schopfer, Don K G
O O
ir ase IRC Chmn: smgh. Anand K Q
C 1/21/96 Date:
INVALSO:
Date:
REs0LUTION Previously 6 den med by NU? C) vos
(#1 No Non Discrepent Condition?C) Yes @ No e
Resolution Penomg?O ve.
<s) No Resolutx>n Unresolved?O ve.
- s) No Review Acceptable Not Acce.* table Needed Date VT i.ned: Nerl, Anthony A VT Mgr: schopfer, Don K IRC Chmn: segh, Anand K Date:
sL Comments:
_ _ _.fhnted 1/22981:11:24 PM -
Page 1 of 1 I
l 5
e
1 m
i Northeast Utilities ICAVP DR No. DR MP3-0072 uniistea unit 3 Discrepancy Report Revtew Group: Prograrrunste DR INVALID Revh Element: Correctu A%on Process p
tht%e: Opershone fg y Diecropency Type: CorrectNo Acton Om SystemProcoes: OSS NRC We level: 4 Date faked to NU:
Date Publisas 1/259e D6ecrepancy: Insufficient Correcthie Action
==
Description:==
UIR 776 states that during an AWO review, it was establisthed that pump SQSS*P3A was run dead headed for approximately 1 ; minutes with indications of some temperature increase. The UlR states further that no non-conformance document was issued or that the pump had been evaluated for potential damage. The corrective action for the UIR was the initiation of an AR for the system engineerto determine if additional action / surveillance is requirW for the pump. The UIR was closed based on th Is AR. Closure of this UIR based on the identified corrective action is inadequate due to potential operability problems. Additionally, an ACR should have been initiated, rather than an AR, as was done in a Olmilar situation for pump 30SS*P1 A under UIR 744 Review Vand invaNd Needed Date initiator: Wrone, S. P.
O G
O ti21ae VT Lead: Ryan, Thomas J Q
[
1/2wd VT Mor: Schopter. Don K O
O O
IRC Chmn: Skgh, Anand K O
O O
Date:
1/21/98 INVALID: The issue in this DR has been combined and included in DR-0916.
Date:
RESOLUTION:
Previously idenGaed by Nu? O Yes G) No NonniscrepentCondition?O Yes @ No Resoluuon Pending?O Yo.
+ iio Resoiuiion unr.coeved?O Yes @ No Review Accepts.ble Not Acceptable Needed Date VT Leed: Ryan, Themes J VT Mgr: Schopfer, Don K IRC Chmn: Sngh, Anand K Date:
SL Conenents:
Printed 1/22/981:12:12 PM Page 1 of 1
- - - _________-_---___--_-_-_-___________ ---