ML20210L872
| ML20210L872 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/19/1997 |
| From: | Schopfer D SARGENT & LUNDY, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-9583-100 NUDOCS 9708210331 | |
| Download: ML20210L872 (28) | |
Text
.
Sar ger6%Lundy" c W.#
l Don K.jgh0P ot' l
p 312 269-6078 August 19,1997 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 twenty (20) discrepancy reports (DRs) identified during our Programmatic Review activities for the ICAVP. These DRs are being distributed in accordance with the Communications Protocol, PI-MP3-01.
- DR No. DR-MP3-0009" DR No.. DR-MP3-0020 r
' DR No. DR-MP3-0010 DR No.- DR-MP3-0021 DR No. DR-MP3-0012 -
DR No. DR-MP3-0022 -
DR No. DR-MP3-0013 DR No. DR-MP3 o023 DR No. DR-MP3-0014 -
DR No. DR-MP3 ;024
- DR No. DR-MP3-0015 DR No. DR-MP3-0025
- DR No.' DR-MP3-0016 -
DR No. DR-MP3-0026 I
DR No. DR-MP3-0017 DR No. DR-MP3-0027
- DR No. DR-MP3-0018 DR No. DR-MP3-0028 f
DR No. DR-MP3 0019 DR No. DR-MP3-0030
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9708210331 970819 l]lll@llllllll]ll lll]l DR ADOCK 05 4y3
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- 55 East Monrce Street. Chicago. IL 60603-5780 USA + 312-269-2000 1
United States Nuclear Regulatory Commission August 19,1997 Document Control Desk Project No. 9583-100 Page 2 Please direct any questions to me at (312) 269-6078.
Yours very truly, b.f N D. K. Sc fer l
Vice President and ICAVP Manager l
DKS:spr Enclosures Copies:
E. Imbro (1/l) Deputy Director, ICAVP Oversight T. Concannon (1/1) Nuclear Energy Advisory Council J. Fougere (1/l) NU mNcavpM7sv0819 a.aw I
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Northeast Utilities ICAVP DR No. DR MP3 0009 Millstone Unit 3 Discrepancy Report ReviewGroup: Accidert Megeten DR VALID Review Element: Modificaton Desgn p
Diecipline: Other Ow Diacrepancy Type: Licensing Document System / Process: N/A NRC Signl5cance level: }
Date faxed to NU:
Date Published:
Diacrepancy: 10CFR 50.59 for ATWS Does Not Address '1ncrease in Feedeter Flo#'
Deecription: The 10CFR 50,59 safety evaluation for the Anticipated Transient Without Scram (ATWS) modification does not address the modification's impact on an increase in feedster flow accident.
The 50.59 addresses the impact of a spurious turbine trip, but coes not address spurious initiation of auxiliary feedwater. This impact needs to be addressed.
Review Valid invalid Needed Date Initiator: Kish, J.
O O
O 701/S7 VT Lead: Rahap. Raj D Q
Q Q
701/97 VT Mgr: Schopfer, Don K Q
O O
alss7 1RC Chmn: Singh, Anand K 8
O O
8/15S7 Date:
l INVALID:
I Date:
RESOLUTloN:
Previously identified by NU7 O Yes @ No Review Acceptable Not Acceptable Needed Date VT Lead: Rahe}s, Raj D VT Mgr: Schopfer, Don K IRC Chmn: Singh, Anand K Date:
SL Comments:
Prited 8/18s97 5.20:50 PM Pege 1 of 1
m.-
dorthent utstin lCAVP DR No. DR MP3 0010 waistone Unit 3 Discrepancy Report l
Revieworoup: Acc6dert Maccan DR VAUD Revlow Element: Syrian Des 6pn pgg,g Diecipune: otho' O ve.
l Diaotopency Type: Licenang Documers Y No l
system /Proceae: N/A
^
NRC 86gnificexe level: 3 De FM@ NU:
l Dale Publ6ehed:
06ecr*Pency: SER $15.4.3 requirement to perform cyde spedfic analysis demonstrating DNB limits are rtot exceeded Descriptiem The Millstone 3 SER, $15.4.3, " age 15-9, dtes the case of rod duster contiel malfunctions Wth rod locations where the reactor does not scram, in this case.le automatic controller may return the reactor to full power and the control could result in a power overshoot. The NRC revleed a generic analyels of this case.
The staff accepted the generio results but noted that the results are reactor and cyde spedfic. Therefore, as an interim positinn, pending the completion of Millstone cyde spedf:c analyses, the staff imposed a restriction for operation above 90% power such that either the reactor is in manual control or rods are required to be out more than 215 steps.
Millstone 3 SSER Supplement 1, $15.4.3, page 151, cite = ^-
completion of the requested analyses for fuel cyde 1 and removes the operating restriction for operation above 90%
power. The SSER states that Amendment 12 to the FSAR Induded a discussion of this event and the results of the analysis. The results are found acceptrible for fuel cyde 1 for N and N 1 loop operation. The continuing requirement to ana!yze future reload cydes remains in place.
Millstone 3 SSER Supplement 3, $15.4.3, page 151, dies the review and acceptance of the generic resolution to this issue.
However, the SSER maintains thrt the ' solution requires a reactor cyde specific analysis shoWng that departure from nudeste bolling (DNB) limits Wil not be exceeded.'
Beyond fuel cyde 1, including the Vantage SH Fuel analyses, no mention of results of these analyses are found in the FSAR, reload analyses or supplements to the SER. There is a continuing fuel cyde spedfic analysis requirement that is not documented.
Rev6ew Vaind inveild wooded Date initteton Peebles.W. R.
Q Q
Q BnS7 VT Lead: Rahoja. Raj D Q
Q Q
BnS7 VT Mgn Schopfer. Don K O
O O
ass 7 1RC Crvnn: Singh, Anand K O
O O
an2s7 Date:
INVALID:
Date:
RESOLUTION:
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Northeest Utilities ICAVP DR No. dR MP3 0010 Millstone unn 3 Discrepancy Report r....--_,-......,y,,,,
,,,y Review Ce* mew NMAff* M NW Date j
inkletor: Poetes, W. R.
D O
O i
VT Lead: Rahele, Raj D O
O O
VT Mgr Schopfer, Don K U
1RC Ctenn: GNh, Anand K O
O oeio:
SL Commeeds:
1 PrWed M&97 5 3 56 PM p,
Northeest Utilities ICAVP DR No. DR MP34012 Millstone Unit 3 Discrepancy Report Rev6ewGroup: Accidwt MAgation DR VALID Review Element: System Desagn Diecipline: I & C Des 6gn PotentW OpwaWNy im Q y,,
Descrepancy Type: Licens10 Docunwit 4 94,
system / Process: f4/A NRC signancance level: h Date faxed to NU o.ie. oho.:
D6wsepancy: inconsistencies in MP 3 FSAR, Technical Specifications, and Westinghouse Safety Analysis Deectlption: We have reviewed the follovdng Millstone 3 documentation:
A) MNPS 3 FSAR, Chapter 15, June 1996; B) Updated page markups for FSAR, Chapter 15 as reviewed and submitted by Westinghouse under letter # NEU 96-623, dated November 25,1996; C) MNPS-3 FSAR Figure 7.21, June 1996; D) Technical Specifications, Millstone Nuclear Power Station, Unit No.3, Docket No. 50-423 Table 2.21 as amended on pages 2-5 through 212, May 2,1997.
Based on the review of these documents we have noted the i
follovdng :
1 FSAR Chapter 15, Table 15.04 identifies a Reactor Trip Function of 'high steam generator level" under transient 15.1, This function is also mentioned in the FSAR section 15.1.2.2 -
discussions of the analysis.
- 2. Westinghouse markup of analysis, Table 15.04 also identifies a Reactor Trip Function of 'hlgh steam generator level" under transient 15.1 The Westinghouse discussion of the analysis under section 15.1.2.2 also includes this function,
- 3. FSAR Chapter 7. Figure 7.21, sheets 1 through 19, do not include a 'high steam Generator level" as a Reactor Trip Function.
- 4. Technical Specifications. Table 2.21 does not include a "High Steam Generator Level"in the tabulation of setpoints for Reactor Trip Functions.
Items 3 and 4 above show the current plant configuration. Items 1 and 2 are incorrect. This discrepancy needs resolution.
Review Valid invalid Needed Date
'nitiator: Balodis, V. E.
O O
O Bra 7 VTLead: Rahoja, Raj D 0
0 0
8FA7 VT Mgr: Schopfer, Don K Q
Q D
8FA7 IRC Chmn: Singh. Anand K O
O O
8/187 Printed Bn847 53 37 PM Page 1 of 2
9 Northeest Utilities ICAVP DR No. DR MP3 0012 uitstore unit 3 Discrepancy Report mammmmma 4;mmmmma w - -
Date:
INVAllD:
Date:
RESOLUTION:
Prov6ously 6dentined by NU7 O Yes
- 9) No Review
- 'N "
initiator: Belodia, V. E.
D D
VTLead: Rebels. Raj D VT Mgr: Schopfer, Don K IRC Chmn: Singh, Anand K
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-a, SL Commenta:
9 4
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n Prvted 0/1897 5 3 46 PM Page 2of 2 1
e Northeast UtWties ICAVP DR No, DR4tP3 N13 Milistone unit 3 Discrepancy Report Rev6ewGroup: Accidert Megation DR VAUD Review Demonit: System Doogn pg l
D6ecipline: I s C Des 6pn Om Diecrepancy Type: Desgn Control Procedwo system / Process: N/A yg NRC signinconce level: 3 Date faxed to NU:
Date Published:
1
~
D6screpancy: Impact of Re-Analysis of Transients and Accidents
==
Description:==
We have reviewed the folloWng MP 3 documents:
A) NGP 3.12 Safety Evaluations, Rev 9, April 7,1995; B) NGP 4.03 Changes and Revisions to Final Safety Analysis Reports,Rev.7,Nov, 4,1996.
C) Updated page markups for FSAR, Chapter 15, ACCIDENT ANALYSIS,as reviewed and submitted by Westinghouse under letter # NEU-96-623, dated November 25,1996.
The Chapter 15 Accident Analysis markups by Westinghouse, referenced above, include accidents which have been reanalyzed and/or accidents with additional information.
Although the limits and consequences may remain within the
(
previously analyzed boundaries the methods, processes, or systems used to mill 0 ate the consequences of an accident may require changes based on the analysis and additional information submitted to NU by Westin0 house.
For exampl6, Figure 15 0 9 that is used to represent the results of the accident " EXCESSIVE LOAD INCREASE" vAlch us analyzed in section 15.1.3 and marked up in the Westinghouse letter, added a "L.ow Pressurizer Pressure" and " Manual" to trip the Reactor Trip System to mitl0 ate the transient. Also, a Note 3 us added which states the folloWng: " Note that safety valve cetpoints are not reached in the analysis of the Section 15.1.3 event."
NGP 3.12 provides guidance for safety evaluations including those resulting from transient and accident analysis. This is discussed in some detail in Attachment 8.A to this procedure.
I There are no identifiable steps or Guidance in this procedure to evaluate the potential impact on training material, simulator scenarios, other calculations, etc.
4 NGP 4.03 provides guidance to screen and implement changes to Final Safety Analysis Report that summarizes the numerous calculations, analyses, evaluations, design information and plant descriptions.
There are no identifiable steps or guidance in this procedure to evaluate the potentialimpact of analysis results on training material, simulator scenarios, other calculations,etc.
Both of these procedures may be suppotied by lower tier procedures. If that is the case, identify the F tx:edures that Prtrud 8n8,97 s 31:2o PM Pege 1 of 2
Northeast Utilities ICAVP DR No. DR-MP3 0013 Millstone Unit 3 Discrepancy Report evaluate the impact of the results of analysis on plant procedures. The impact of Westinghouse reanalysis for each reload cycle requires an assesment.
Review Valid inval6d Needed Date inMietor: Dalode 1. E.
O O
O ara 7 VTLeaJ: Rahoje. Raj D C
O D
bra 7 VT Mgr: Schopfer Don K O
O O
aw7 IRC Chmn: $1ngh, Anand K O
O y
artis7 Date:
INVALID:
Date:
RESOLUT10N:
Prev 6ously identified by NU7 () Yes iG) No Rev6ew cc$2 Acc $ a W NW be inMistor: Danodes, V. E.
D O
O VT Lead: Rahets, Raj D O
O O
VT Mgr: Schopfer, Don K IRC Chmn: Singh, Anand K Date:
SL Comments:
PrWed 6/18S7531% PM Page 2 of 2
Northeast Utilities ICAVP DR No. DR-MP3 0014 Ministone unit 3 Discrepancy Report Review Oroup: Programmatic DR VAUD Review Dement: Correathe Action Process p
Diecipune: Qher O vee Diacropency Type: Licensing Documert
? No system /Procate: Rss NRC Significance level: 3 page faxed to NU:
Date Publiehod.
Diecrepancy: Inadequate Response on How Action Will Prevent Recunence (ACR#M3-961015)
Deecti t6on: The Ucensee's response in the ACR documentation on how P
corTective actions will prevent or reduce the possibility of recurrence is inadequate.
Amendments 100 and 122 of Tech. Specs. were issued using an l
out of-dato revision of Tech. Specs. This vas documented on i
j ACR M3 51015. ACR M3-961015 (block 6 of form RP 41) l recommends that "Ucensing dept. should investigate the cause for this condition and propose corrective actions to prevent recurrence." Contrary to the recommendations, the ACR Indicates on Form RP 4-8 that a causal factor determination is not required. In block 7 of form RP 4-7, the Ucensee is required to state "how the corrective actions will effectively prevent or reduce the possibility of the same or sirrdlar event or adverse condition from happening again", The Ucensee's response to this question is " Administrative Enor Correction Needed." No evidence is provided to indicate that the actual mechanism by vAlch the administrative error occurred ves determined (le., how vas the wrong revision of Tech. Specs used to process new Tech Spec. Amendments, are procedural controls for processing Tech. Spec. Amendments adequate? etc.) and that any specific action is planned to prevent recurrence as recommended by the initiatorof the ACR.
Review Valid Invalid Needed Date inMietor: Neerro, Mark Q
Q Q
7f3147 VT Lead: Ryan, Thomme J Q
Q Q
8/497 VT Mgr: Schopfer. Don K Q
Q Q
BGB7 IRC Chmn: Singh. Anand K Q
Q Q
85597 D.i.:
INVALID:
Date:
REsoLUTloN:
Previously idonufted by NU7 C) Yee @ No Review initiator: Neverro, Mark VT Lead: Ryan, Thomme J VT Mgr: Schopfer, Don K 1RC Ctenn: Singh, Anand K Date:
Ri CWhmeOta?
Prwted 858.9752134 PM Pege1 of 2
Northeast Utilities ICAVP DR No. DR MP34014 1
Millstone Unit 3 Discrepancy Report 1
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PrWed 85&97 5 214 PM Pop 2 d 2 i
a Northeest Utilities ICAVP DR No. DR MP3 0015 Milistone unit 3 Discrepancy Report ReviewGroup: Accidert Maigaton DR VAL.1D N'**N#IM M" Polential operstdisty leeue Diecipline: Wier O vee Diacrepancy Type: Calculeon
(*) No system / Process: N/A
~~
NRC Significance level: 3 De W W Dale Published:
bleueponey: Compliance Wth GDC 19 Deecristion: A review of the folloWng documentation has concluded that a discrepancy exists Wth regard to documented compliance Wth the Millstone 3 Operating Ucense, FSAR and GDC 19 as they
- r. hate to the estimated dose received by the operators folloWng postulated design basis accidents. The documents reviewed are:
- 1) MP3 FSAR Tables 6.4-1 and 9.4-2
- 3) MP3 Ventilation Systems DBD
- 4) MP3 Tech. Spec. 3/4.7.7 - Control Room Emergency Ventilation System
- 5) MP3 Control Room Dose Calculations [UR(B)-365-1; UR(B)-
366-1; UR(B)-3671l and 88-019-97RA, Rev. 0]
- 6) UIR 343 The MP3 Technical Specification indicates that the desl n and 0
tested flow rate for the control room emergency filter system is 1120 cfm +/- 20%. Based ori dils specification, the flowcould range from 896 to 1344 cfm. This value is different from that reported in the FSAR and the DBD. The referenced dose calculations are the calcelations of record to show compliance with control room habitability requirement! ?t Millstone 3. The calculations use a value of 1000 cfm for the flow rate of this safety system. This value differs from the reported Technical Specification value. Since the flowrate through these filters directly affects the estimated post LOCA dose to the operators, a concem exists regarding NU compliance Wth the Millstone 3 FSAR estimates for post-LOCA operator doses and General Design Criteria (GDC) 19. Use of a filter flow rate other than that vAlich is put out by the control room emergency filter unit may be non-conservative.
GDC 19 requires that the operators be provided Wth a control room from which actions can be taken to operate the nuclear power plant saf ely under normal conditions and to maintain it in a safe condition under accident conditions, including a loss-of-coolant accident (LOCA). It is this latter capability that is under question in this discrepancy report, NU has identified an unresolved issue report (UIR 343) that a discrepant condition exists with regard to the reported flow Prtted 85897 5:3242 PM Page 1 of 2
Northeest Utilities ICAVP DR No. DR-MP34015 milistone unit 3 Discrepancy Report values in the Millstone 3 Technical Specifications and FSAR for the control room emergency filter system. The UIR condudes that actions in ACR 8843 and A/R 9600766 Wil process the FSAR change required to resolve the condition and states that no additic.nal action is required, While these actions note the FSAR discrepancy, there is no objective evidence that NU has appropriately addressed the issue in the design calculations.
Revle.v Valid invalid Nooded Date initiatort Bennett, L. A.
O O
O SSS7 VT Lead: Raho)s RajD D
D O
aser VT Mgr: Schopfw, Don K O
O O
eser IRC Civnn: Shgh, Anand K O
O O
aner Date:
INVAllD:
Date:
RESOLUTION:
PNviously idenoned by NU7 V Yes @ No Review inittetor: Bennett, L. A.
VT Lead: Rahele, Raj D VT Mgr: Schopfw, Don K IRC Clenn: Wh, Anand K
- e:
SL Commenta:
I
=
Prated mas 7 5M23 PM Page 2 of 2
Northeast Utilhies ICAVP DR No. DR-MP3 0016 Millstone unM 3 Discrepancy Report ReviewGroup: Accklord Megaton DR VALID Review Element: System Desgn Diecipline: othw Phi opwebliny leeue
()y,,
Diecrepancy Type: Licenang Documert
,9) No System /Procoes: N/A
~
NRC signiecance level:
Date faxed to NU:
Date Published:
D6ewspancy: Incorrect Values in FSAR Table 15.7 9 Deectlpt6on: We have reviend calculation XX-XXX-107RA, Revision 0,
" Radiological Consequences of a Fuel Handling Accident at MP-3," for constrJency Wth the input data and assumptions (including critical system characteristics) and results presented in Chapter 15 of the FSAR. The two documents are in agreement except for some items in Table 15.7 9, "Activilles Released to the Environment As a Result of a Fuel Handling Accident in the Fuel Building " These items are:
- 1. The activity for Isotope I 130 is listed in the table as 1.31E+0). The results of the calculation indicate the actual activity is 1.31E-03.
- 2. The isotope identified as Be-82 should be Br 82.
- 3. In the second Note the numerical value 5.71 should be chan0ed to 6.10 to ba consistent Wth the value in the table.
The first item should be corrected since it implies an incorrect basis for the offsite dcse presented in Table 15.0-8 (vAlch is in agreement Wth the calculation). The other tm items are editorialin nature.
A review of the UIR database did not identify any items related to this section of the FSAR.
The above inconsistancies need resolution.
Review Valid inveild Needed Date Initiator: Johnson, W. J.
O O
O 7c187 VT Lead: Rehoja,RelD 0
0 0
7a187 VT Mgr Schopfw, Don K O
O O
ase7 1RC Chmn: Sin 95, Anand K O
O O
anwo7 Date:
INVALID:
Date:
RESOLUTION:
Previously identined by NU7 (.) Yee it) No Review initiator: Johnson, W. J.
VT Lead: Rahese. Rej D VT Mgr: Schopfw, Don K Pnnted D'18/97 5 34 38 PM Pe0* 1 of 2
No% east UtiWes ICAVP DR No. DR44P3.500 Millstone unit s Discrepancy Report O
O e
O O
O IRC Chmn: Singh, Anand K o.i.:
f SL Comments:
PtWed 8/1847 53451 PM Pege 2 of 2
Northeest Utilities ICAVP DR No. DR-MP3 0017 M661 stone Unit 3 Discrepancy Report Revieworoup: Accidert Milgeton DR VAllD Review Element: System Desgn Diecipline: oth*'
Potential operability leeue Ow Diecrepency Type: Licensng Documert
(#1No System /Procese: N/A
~
NRc Significence level:
Date faxed lo NU:
Dele Pubilehed:
Diecrepancy: Westinghouse Comments on FSAR Chapter 15.0
==
Description:==
We have reviewed Westinghouse Electric Corporation letter NEU-96-623, Northeast Utilities Service Company Millstone Unit 3 FSAR Chapter 15 Verification - non-LOCA," dated November 25,1996, vhich provided NU suggested page markups for FSAR Section 15.0, Introduction. The purpose of these comments and markups Yes to provide assurance that the Millstone 3 FSAR is consistent Wili the Plant Safety EvhNation of record for the current fuel cycle.
The comments on this section identify clianges to the initial conditions, nominal values and the reactcr and ESF trip functions and sequence of event diagrams for the accidents in Westinghouse scope. These changes have not been incorporated into the FSAR making the FSAR and the Plant Safety Evaluation inconsistent.
A review of applicable cosrective action databases for Millstone 3 has not identified any pending FSAR change notice items that Wil incorporate the Westinghouse comments into the FSAR, Review Ve46d invalid Needed Dele inatiator: Johnson, W. J.
Q Q
Q Mis 7 VT Lead: Reheie,RajD D
D O
MSS 7 VT Mgr: Schopfer, Don K O
O O
M1S7 IRc Ctenn: Singh, Anend K Q
Q Q
M2/97 Date:
INVAllD:
Date:
REsoLUT10N:
Previously identified by NU7 O Yes LO' No Review Ac optable Not Acceptable Needed Date inh: Johnson, W. J.
VT Lead: Rehese, Raj D VT Mgr: Schopfer, Don K IRc Chmn: Singh, Anend K Date:
SL Comments:
Prtrted MBS7 5303 PM Page 1 of 1
Northeest Utilities ICAVP DR No. DR MP3 0018 Ministone unit 3 Discrepancy Report ReviewGroup: Operet ons & Melntenance and Testing DRVAUD Review Elmnent: Test Procedure pggg
,gy gg, Diecipline: Operatons O Yee Discreparwy Type: 0 & M & T Procedure
(*) No SystemIProcess: R NRC Signancance level:
Date faxed to NU:
Date PublietM:
Discreparry: MISIDENTIFIED PUMP DESIGNATOR IN STEP OF PROCEDURE Deecripuon: CONTAINMENT RECIRCULATION PUMP 3RES*P1 A OPERATIONAL READINESS TEST SP 3606.1 REV.10, CH,1 STEP 4.4.12.1, LAST BULLET STATES:"CLOSE and LOCK 3RSS*V958, containment recirculation pump C discharge header vent".
The Step should be corrected to read ' containment recirculation pump A discharge header Vent'.
Review Val 6d invelld Needed Date initiator: Ungeren, R.
O O
O M *7 VT Lead: Queno, Robert E O
O O
MS7 VT Mgr: Schopfer, Don K O
O O
8'd7 1RC Chmn: Singh, Anand K G
O O
m S7 Date:
INVAUD:
Date:
RESOLUTION:
Previously idenufled by NU?
(,) Yes
- 69) No Revlow initiator: Ungeren, R.
VT Lead: Querio, Robert E
~
VT Mgr: Schopfer, Don K IRC Chmn: Singh, Anand K O
O O
D.i.:
SL Comments:
PrWed M897 5.38.11 PM Page 1 of 1
Northeast Utilities ICAVP DR No. DR MP3 0019 Millstone Unit 3 Discrepancy Report Revieworoup: ACCKleftIMgeten DR VAllD ReviewElement: System Design Diecipline other p,ggg op,gy g.
O Ya Discrepancy Type: Licensing Documert
'#1No System /Procese: N/A
~
NRC Significance level:
Date faxed Io NU:
Date Pubtlehed:
Discr*Pency: Westinghouse Comments of FSAR Section 15.1 De=Cri tion: We have reviewd Westinghouse Electric Corporation letter P
NEU 96-623, Northeast Utilities Service Company Millstone Unit 3 FSAR Chapter 15 Verification - non-LOCA," dated November 25,1996, which provided NU suggested page markups for FSAR Section 15.1, increase in Heat Removal by the Secondary System. The purpose of these comments and markups us to provide assurance that the Millstone 3 FSAR is consistent Wth the Plant Safety Evaluation of record for the current fuel cycle.
The comments on this section identify changes to the input l
assumptions, time sequence of events and results for the accidents analyzed in this section. These changes have not been incorporated into the FSAR, making the FSAR and the Plant Safety Evaluation inconsistent, A review of applicable corrective action databases for Millstone 3 has not identified any pending FSAR change notice items that Wil incorporate the Westinghouse comments into the FSAR, Review Valid invalid Needed Date Initiator: Johnoon, W, J.
O O
O MSS 7 VT Lead: Rehele, Raj D Q
Q Q
M147 VT Mgr: Schopfer, Don K O
O O
M187 IRC Chmn: Singh, Anand K O
O O
m2s7 Date:
INVAllD:
Date:
RESOLUTION:
Previously identified by NUP O Yes ;en No Review initiator: Johnson, W. J.
VT Lead: Rahoja, Raj D VT Mgr: Schopfer, Don K IRC Chmn: Singn, Anand K Date:
SL Ctenments:
Printed M847 539ot PM Page 1 of 1
_ _ _ - _ _ _ ~. _ _ _ _ _ _.
.r Northeast Utilities ICAVP DR No. DR MP34020 Millston* Unit 3 Discrepancy Report Rev'owGroup: Acc@wt MAgaton DR VAUD Review Eternent: System Des 9n Diecip44ne: Uh*'
Potwia@W6My im O ve.
Dieuepancy Type: Licensing Documert Si No System /Procese: N/A NRC Signincance level:
f.
Date faxed to NU:
Date rub w d:
D6ewep*ert Westinghouse Comments on FSAR Section 15.0 and 15.6 Deewspoon: We have reviewed Westinghouse Electric Corporation letter NEU 96-615. " Northeast Utilities Service Company Millstone Unit 3 Review of FSAR Chapter 15. LOCA," dated November 1, 1996, which provided NU suggested page markups for FSAR Section 15.0, introduction, and Section 15.6, Decrease in Reactor Coolant Inventory. The purpose of these commerts and markups was to provide assurance that the Millstone 3 FSAR is consistent Wth the Plant Safety Evaluation of record for the current fuel cycle.
The comments on this section identify changes to the input assumptions and results for the accidents analyzed in this section. The Westinghouse changes leave unresolved the observation that the analysis was performed using a 2% loop uncertainty Wiereas the FSAR lists the N 11oop uncertainty as 2.3%. These changes have not been incorporated into the FSAR, making the FSAR and the Plant Safety Evaluation inconsistent.
A review of applicable corrective action databases ftr Millstone 3 has not identified any pending FSAR change notice items that vAll incorporate the Westinghouse comments into the FSAR, Revieve Val 6d invalld Needed Date Initialor: Johnson, W. J.
'Q Q
Q M147 VT Lead: Rahoja, Raj D D
D D
M1S7 VT Mgra Schopfer, Don K Q
Q Q
M147 IRC Chmn: Singh, Anand K O
O O
M2S7 Date:
INVAUD:
Date:
RESOLUTION:
Previously identined by NU7 O Yee t No Review inilletor: Johnson. W. J.
VT Lead: Rahoja, Raj D VT Mgr: Schopfer, Don K IRC Ctwnn: Singh, Anand K Date:
SL Comments:
Prrted 8/18S7 5 4052 PM Page 1 of 1
Northeast Utilities ICAVP DR No, DR-MP3 0021 Mmstone Unit 3 Discrepancy Report ReviewGroup: Accusert Megation DR VALID Review Element: Systern Desen D'**'P"a': **'
pyg,; pay g.
O ve.
Diecrepancy Type: Ocensing Documort iei No SystemIProcess: N/A
~
' NRc sign 6nconce level: y Date faxed to NU Date Published:
D6screpancy: Westinghouse Comments on FSAR Section 15.0 Descripuon: We have reviewed Westinghouse Electric Corporation letter NEU 97 536, Northeast Utilities Service Company Millstone Unit 3 Review of FSAR Chapter 15," dated April 8,1997, Wilch provided NU suggested page markups for FSAR Section 15.0, introduction. The purpose of these comments and markups was to provide assurance that the Millstone 3 FSAR is consistent Wth the Plant Safety Evaluation of record for the current fuel cycle.
l The commerits on this section identify changes to Figure 15.0 21 i
and Table 15.0-2. These changes have not been incorporated into the FSAR, making the FSAR inconsistent Wth the Plant l
Safety Evaluation.
A review of applicable corrective action databases for Millstone 3 has not identified any pending FSAR change notice items that Wil incorporate the Westinghouse comments into the FSAR.
Review Vand invalid Needed Date initiator: Johnson, W. J.
O O
O M '/87 l
VT Lead: Rahoja. Raj D D
O O
Mido7 VT Mgr Schopfer, Don K Q
O O
Mids 7 IRC Chmn: Singh, Anand K O
O O
M do7 D.ie:
INVAUD:
Date:
RESOLUTION:
Previously identined by NU7
(_) Yes JG) No Review ccMa ec $ a NW be inhistor: Johnson, W. J D
O O
VT Lead: Rahoje, Raj D VT Mgr: Schopfer, Don K IRc Chmn: Singh, Anand K t..
SL Comments:
Prvted MOS7 5 4352 PM Page 1 of 1
Northeast Utilities ICAVP DR No. DR MP3-0022 mistone unit 3 Discrepancy Report ReviewGroup: Accmert Megaten DR VAllD Review Element: System Deegn PotentW OperebilNy lease Disc W M *r O y,,
Discrepency Type: Licensing Documort 4 g, system /Proceae: N/A NRC sipdftcence level:
Date faxed to NU:
Dele Putd6ehed:
Diecropency: Westinghouse Comments on FSAR Section 15.1 Descrl tion: We have revloed Westinghouse Electric Corporation letter P
NEU-97 537," Northeast Utilities Service Company Millstone Unit 3 Review of Steam Une Break M&E Information in FSAR Chapter 15," dated April 8,1997, which provided NU suggested page markups for FSAR Section 15.1, increase in Heat Removal by the Secondary System. The purpose of these comments and markups was to provide assurance that the Millstone 3 FSAR is consistent Wth the Plant Safety Evaluation of record for the current fuel cycle.
The comments on this section identify changes to the input assumptions for the accidents analyzed in this section. The changes have not been incorporated into the FSAR, maldng the FSAR inconsistent Wth the Plant Safety Evaluation.
A review of applicable corrective action databases for Millstone 3 has not identified any pending FSAR change notics items that Wil incorporate the Westinghouse comments into the FSAR.
Review Veled involid Needed Date initietor: Johnson, W. J-O O
O mia7 VTLeed: Rehete RajD D
D D
m S7 VT Mgra Schopfer, Don K O
O O
mis 7 IRC Chmn: Singh, Anand K O
O O
e:*7 Dele:
INVAL10:
Date:
~
RESOLUTION:
Previously identifled by NU7 (,) Yes tS) No Rev6ew CCePteW N AccepeW NW Me inMietor: Johnson, W. J.
VT Leed: Reheie, Raj D VT Mgr; Schopfer, Don K IRC Chmn: Singh, Anand K Dete:
SL Cornmente:
Prvted MBS7 5 626 PM Page 1 of 1
i Northeast UtilHies ICAVP DR No. DR MP34023 Millstone unk 3 Discrepancy Report ReviewGroup: Accusert Megeton DR VAUD Review Element: System Desgn Diecipline: Other Potential Operaldlety leeue Q y,,
Dieceopency Type: Licensirg Documert
,, No SystemIProcess: N/A NRC Significance level: h a
Date rAXed to NU:
Date Published:
dim 8 +Pancy: Westinghouse Comments on FSAR Section 15.4 Descript6on: We have reviewed Westingbouse Electric Corporation letter NEU-96423, Northeast Utilities Service Company Millstone Unit 3 FSAR Chapter 15 Verification non-LOCA," dated November 25,1996, VAlch provided NU suggested page markups for FSAR Section 15.4, Reactivity and Power Distribution Anomalies. The pwpose of these comments and markups was to provide assurance that the Millstone 3 FSAR is consistent Wth the Plant Safety Evaluation of record for the current fuel cycle.
The comments on this section identify changes to the input assumptions and results for the accidents analyzed in this section. These changes have not been incorporated into the FSAR. making the FSAR and Plant Safety Evaluation inconsistent.
A review of applicable corrective actinn databases for Millstone 3 has not identified any pending FSAR change notice items that Wil incorporate the Westinghouse comments into the FSAR.
Review Valid invol6d Needed De's initiator: Johnson. W, J O
O O
M187 VT Leed: Rahela. Raj D D
D D
MSS 7 VT Mgri Schopfer, Don K O
O O
M587 IRC Chmn: Singh, Anand K O
O O
m2s7 Date:
INVAllD:
Date:
RESOLUTloN:
Previously identined by NU7 U Yes 191 No Review initiator: Johnson. W. J.
VT Lead: Rahoje, Raj D VT Mgr: Schopfer, Don K 1RC Ctenn: 54ngh, Anand K o..
SL Commente:
Prtried MBS7 551:31 PM Pope 1 of 1
Northeast Utilities ICAVP DR No. DR-MP3-0024 Ministone unit 3 Discrepancy Report ReviewGrpup: Accowt Magate DR VAL'O Review Element: System Deegn Diecipline: Other Potential 0pweyleeue Q y,,
D6ecrePancy Type: Ucensing Documwt
,, y, system / Process: N/A NRC Significance level: f Date faxed to NU:
D.te r.. d:
Diecrepancy: Westinghousr. Comments on FSAR Section 15.4
==
Description:==
We have reviewd Westinghouse Electric Corporation letter NEU 97 536," Northeast Utilities Service Company Millstone Unit 3 Review of FSAR Chapter 15," dated April 8,1997, vAlch p;ovided NU suggested page markups for FSAR Section 15.4, Reactivity and Pour Distribution Anomalies, The purpose of these comments and markups was to provide assurance that the Millstone 3 FSAR is consistent with the Plant Safety Evaluation of record for the current fuel cycle.
The comments on this section identify changes to the description of the results for the accidents analyzed in this section. These changes have not been incorporated into the FSAR, making the FSAR and the Plant Safety Evaluation inconsistent.
A review of applicable corrective action databases for Millstone 3 has not identified any pending FSAR change notice items that vdll incorporate the Westinghouse comments into the FSAR.
Review Valid Involid Needed Date initleter: Johnson, W. J, O
Q Q
8/11 s 7 VT Lead: Rahoje, Raj D Q
Q Q
8/1147 VT Mgr: Schopfe, Don K O
O O
ariis7 I
1RC Chmn: Singh, Anand K G
O O
Bri2s7 Date:
INVAllD:
Date:
RESOLU1)ON:
Previoualy identified by NU7 C) Yes 18' No Review
^***
- inittetor: Johnson, W. J.
D 0
0 VT Lead: Rehop, Raj D VT Mgr: Schopfer, Don K IRC Chrnn: Singh, Anand K Date:
SL Comments:
Prvted 8/1847 553 o3 PM Pope 1 of i
e Northeast Utilit6es ICAVP DR No. DR-MP3 0026 mistone Unit 3 Discrepancy Report ReviewOroup: Accadert Mtgatm DR VALID Review Dement: 6ptem installaton Diecipline: I & C Desgo PMW OperabHay leeue O yeo Disaepancy Type: Licenssng Documort (S)No System /Proceae: N/A NRC signincance level: }
Date faxed to NU:
Date Published:
Discrepancy: UFSAR Discrepancy Regarding ATWS TurDine lmpulse Pressure Signal
==
Description:==
UFSAR, Rev,05/01/97, Chapter 7.8, page 7.8 2 contains the d
folloWng statement "AMSAC also utilizes the turbine impulse pressure signal for measuring a pressure rise in the turbine, as measured Wth the pressure transmitters located in tne steam supply line near the turbine...".
A reviewof P&lD EM 123C 12 identified the referenced pressure transmitters / sensors as corTectly reading pressure at a location inside the high pressure turbine Casing and not in the steam supply line near the turbine.
Review Valid invalid Needed Date Initiator: Kish, J.
O O
O ans7 VT Lead: Rahep, Raj D O
O O
MS7 VT Mgr: Schopfer Don K O
O O
8F*7 1RC Chmn: Singh, Anand K Q
Q Q
BN247 Det.:
INVAllD:
4 Date:
RESOLUTION:
Previously identined by NU7 O Yes
,Si No Review Acceptable Not Acceptable Needed Date VT Lead: Rahep, Raj D VT Mgr: Schopfer, Don K IRC Chmn: Singh, Anand K Date:
sL Comments:
W7 55513 PM Pege 1 of 1
8 Northeast Utilities ICAVP DR No. DR MP3 0026 Millstone Unit 3 Discrepancy Report ReviewGroup: Acc6dert Megetson DR VALID Rev6ew Element: Spiom Degn Diecipline: other Potential Operebility leeue O Yes Diecrepency Type: Licensing Docust (9) No system /Proceae: f4/A
~
NRC significence level:
Dele Faxed to NU:
Date Published:
Discrofancy: Westinghouse Comments on FSAR Section 15.2 Deecripinon: We have reviewed Westinghouse Electric Corporation letter NEU 96-623, " Northeast Utilities Service Company Millstone Unit 3 FSAR Chapter 15 Verification - non-LOCA," dated November 25,1996, Wilch provided NU suggested page markups for FSAR Section 15.2, Decrease in Heat Removal by the Secondary System. The purpose of these comments and markups was to provide assurance that the Millstone 3 FSAR is consistent Wth the Plant Safety Evaluation of recorti for the curTent fuel cycle.
The comments on this section identify changes to the input assumptions and results for the accidents analyzed. These changes have not been irgspriated into the FSAR, making the FSAR and the Plant Safety Evaluation inconsistent.
A reviewof applicatWe corrective action databases for Millstone 3 has not identified any pending FSAR change notice items that Wil Incorporate the Westinghouse comments into the FSAR.
Review Veled invalid Needed Date initiator: Johnson, W, J.
O O
O MSS 7 VTLeed: Rehete, Raj D G
O O
M 'S7 VT Mgr Schopfer, Don K
[
[
M147 IRc Chmn: Singh, Anand K g
Q Q
anOc7 Date:
INVALID:
Date:
RESoLUTlON:
Previously identitled by NU7 O Yes (9) No Review initletor: Johnson, W. J.
b O
VT Leed: Rehoje RajD VT Mgr: Schopfer, Don K IRC Chmn: Singh, Anand K Date:
SL Commente:
Prtrted M847 557 21 PM Pege 1 of 1
Northeast Utiliti..
ICAVP DR No. DR MP34027 Millstone Unit 3 Discrepancy Report ReviewOtoup: Acckfort Mtgeton DR VALl0 Review Element: System Depen p
Diecip66ne: otho' O vee Diacroposey Type: Licensing Documert
.,, g i
8,elem/Proceae: N/A NRC tagedficance level:
Date faxed to NU:
Date Pubilehed:
06ewepency: Inconrect Nuclide Identified in FSAR Section 15.0 Deacti tion: We have reviewed FSAR Chapter 15 and have identified the P
following discrepancy:
In paragraph 15.0.9.2, Inventory in the Fuel Pellet Gap, it is stated that the gap activity is determined using the model in Regulatory Guide 1.25. The FSAR states that this activity includes 30% of the 1117. Reviewof Regulatory Guide 1.25 indicates that this should be 30% of the 1127.
Review Valid invelld Needed Date initiator: Johnson, W. J.
O O
O M *7 VT Lead: Reheja, Raj D G
O O
8 tis 7 4
VT Mgr: Schopfer. Don K O
O O
Brw7 IRC Chmn: 66ngh, Anand K g
Q Q
8//s7 Date:
INVAllD:
Date:
AESOLUTION:
Previounty identified by hU? ( ) Yes
'91 No Review inMhtor: Johnson. W. J.
VT Lead: Rehefe, Rej D VT Mgri Schopfer, Don K IRC Chmn: Singh, Anand K Date:
~
SL Commente:
1 Pnnled 8n847 550:05 PM Page 1 of 1
a Northeaut Utilities ICAVP DR No. DR MP3 0028 Ministone Unit 3 Discrepancy Report ReviewGroup: Ace'dwt Mittoston DR VAUD ReviewElesnent: System Desyn pg,,ggg g,,,g.
Discipline: Oth*'
O Ya Diacrepancy Type: Uconsng Documwt 1,3 g, System / Process: N/A
~
I NRC Significance level: h Date faxed to NU:
Date Published:
Disaepeacy: Inconsistency in FSAR Section 15.7 Deantetton: We have reviewed FSAR Chapter 15 and have identified the follovAng discrepancy:
In Section 15.7.5, Spent Fuel Cask Drop Accidents, Subsection 15.7.6.1, Analysis of Effects and Consequences, the first sentence reads "A spent fuel handling accident is..." This should be changed to "A spent fuel cask drop accident is..."
Review Valid invelld Needed Date inMietor: Johnson, W. J.
Q
[
MS7 VT Lead: Rehele. Raj D Q
Q Q
8/147 VT Mgr: Schopfw, Don K O
O O
ase7 IRC Ctwnn: Singh, Anand K O
O 8/187 Date:
INVAUD:
Date:
RESOLUT10N:
Previously identined by NU7 Q Yes it) No Review inMistor: Johnson, W. J.
VT Lead: Rebeja. Raj D VT Mgr: Schopfer, Don K 1RC Cfwnn: Singh. Anand K O
O
-e SL Comments:
Pnnted 8/18S7 e 0037 PM Page 1 of 1
Northeast Utilhies ICAVP DR No. DR MP3 0030 Millstone unit 3 Discrepancy Report ReviewGroup: Acciant Maget&on DR VAllD Review Element: System Doogn Diecipline: Mechenacel Design Pmh@myim O Yee D6eaepeney Type: Licanang Documort
- ) No S) stem / Process: N/A
'~
NRC signtAcence level: 3 Date faxed to NU:
Date Published:
Diecrepancy: Discrepancy between drawdown times for rod ejection accident and LOCA DeectiPtion: In our review of FSAR Section 15.4.8.4 a discrepancy was noted.,
in FSAR Section 15.4.8.4, the radiological consequerx:es of a postulated rod ejection accident are discussed. It is stated that the assumed time for the secondary containment to drawdown to 0.25"wg is 60 seconds. It is fu@er stated that this 60 second drawdom time is the same as that which was used for the LOCA analysis.
Review of FSAR Table 15.6-9, however indicates that a time of 120 seconds ves used for the LOCA analysis as the drawdom time.
This discrepancy between the two sections of the FSAR needs resolution Review Valid invalid Needed Date ledtletor: Kane,T.J.
O O
O aris7 VT Lead: Rehop,RelD G
O O
at:47 VT Mgr: Schopfer, Don K O
O O
arw7 1RC Civnn: Singh, Anand K Q
Q Q
af147 Date:
INVAllD:
Date:
RESOLUTION:
Previously identified by NU7 Q Yee i9i No Review Acceptable Not Acceptable Needed Date VT Lead: Rehele, Raj D VT Mgr: Schopfer, Don K IRC Ctenn: Singh, Anand K Date:
SL Comments:
Prirted atla /97 e0130 PM Page 1 of 1