ML20217P065

Summary of 970709 Meeting W/Util Re Issues Related to 1996 Rev of McGuire Ufsar.List of Attendees & Verbal Response Encl

ML20217P065
Person / Time
Site:	Mcguire, McGuire
Issue date:	08/22/1997
From:	Nerses V NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
TAC-M97264, TAC-M97265, NUDOCS 9708260431
Download: ML20217P065 (15)

Text

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M Y67 patog p* t UNITED STATES

• } NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30466-0001

'g ,, ( , , August 22, 1997 LICENSEE: Duke Power Compan/

FACILi1Y: McGuire Nuclear Station, Units 1 and 2

SUBJECT:

MEETING

SUMMARY

- REVIEW OF THE 1996 REVISION OF THE UPDATED FINAL SAFETY ANALYSIS REPORT (TAC NOS. M97264 AND M97265)

REFERENCE:

Meeting Notice by V. Nerses dated June 20,1997 On July 9,1997, the staff met with Duke Power Company (DPC) to discuss issues related to the 1996 revision of the McGuire Updated Final Safety Analysis Report (UFSAR).

Enclosure 1 is a list of the meeting participants.

By letter dated November 6,1996, DPC submitted the 1996 revision to the McGuire FSAR in accordance with 10 CFR 50.71. This regulation requiros that the UFSAR:

...shall contain all the changes necessary to reflect information and analyses submitted to the Commission by the licensee or prepareo t by the licensee pursuant to Commission requirement since the submission of the original FSAR or, as appropriate, the last updated FSAR.

Section 50.71 specifies that the update FSAR shall be revised to include the effects of:

1. "All changes made in the facility or procedures as described in the FSAR."

2. " Safety evaluations performed by the licensee either in support of requested license amendments or in suppoit of conclusions that changes did not involve an unreviewed safety question."

3, 4ll analyres of new safety issues performed by or on behalf of the licensee at dommission request."

Accordingly, the purpose of the staff's review was to confirm if the changes made in the 1998 revision comply with the provisions of 10 CFR 50.71, t

o00 g 9708260431 DR 970822 ADOCK 05000369 PDR

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August 22, 1997 In the meeting, DPC verbally responded to questions the staff raised in its meeting notice of June 20,1997. The staff recorded these responses (Enclosure 2) and will use the information, upon proper verification, to complete its review of the 1996 revision of *he McGuira UFSAR.

ORIGINAL SIGNED BY:

Victor Nerses, Senior Project Manager Project Directorate 11-2 Division of Nuclear Reactor Projects - l/II Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370

Enclosures:

1. List of participants

2. Record of licensee's verbal re:ponse cc w/encls: See next page Distribution for Meetina Summary:

HARD COPY Docket File PUBLIC PD ll 2 Rdg.

OGC ACRS E-MAIL S. Collins /F. Miraglia R. Zimmerman B. Boger H. Berkow '

V. Nerses L. Berry D. Ross (e mail to SLM3)

N. Dudley (NFD)

J. Johnson, Ril S. Schaeffer, Ril To receive a copy of this document, indicate in the box: "C" = Copy without attachmentlenclosure " E" =

C::py with attachmentlenclosure "N" = No copy -

OFFICE PM:PDil-2 () LA:PDil-26 D:Ppl p p j l NAME VNerses:cn LBerry M HBerW6W DATE p)/ 7 /97  %/y /97 5

(// g/97 / /97 / /97 / /97 JOCUMENT NAME: G:\MCGUIRE\MEETSUMU.FSA OFFICIAL RECORD COPY

2-In the meeting, DPC verbally responded to questions the staff raised in its meeting notice of i June 20,1997. The staff recorded these responses (Enclosure 2) and will use the information, upon proper verification, to complete its review of the 1996 revision of the McGuire UFSAR.

Victor Norses, Senior Project Manager Project Directorate ll 2 Division of Nuclear Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos.:50-369 and 50-370 '

Enclosures:

1. List of participants

2. Record of licensee's verbal response I

cc w/encis: See next page L

4 s

McGuira Nuclser Station Units 1 and 2 Mr. Richard Fry, Director cc: Department of Environmental, Mr. Paul R. Newton Health and Natural Resources Duke Power Company, PBOSE Division of Radiation Protection 422 South Church Street 3825 Barrett Drive Charlotte, North Carolina 28242 0001 Raleigh, North Carolina 27609 7721 County Manager of Mecklenberg County Ms. l'aren E. Long 720 East Fourth Street Assistant Attomey General Chartotte, North Carolina 28202 North Carolina Department of Justice Mr. Michael T. Cash P. O. Box 629

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Regulatory Compliance Manager Raleigh, North Carolina 27602 McGuire Nuclear Station y] Duke Power Company Mr. G. A. Copp L3 12700 Hagers Ferry Road Licensing - EC050 Huntersville, North Carolina 28078-8985 Duke Power Company 526 South Church Street J. Michael McGarry,111. Esquire Charlotte, North Carolina 28242-0001 Winston and Strawn 1400 L Street, NW. Regional Administrator, Region ll Washington, DC 20005 U.S. Nuclear Regulatory Commission Atlanta Federal Center Senior Resident inspector 61 Forsyth Street, S.W., Suite 23T85 clo U. S. Nuclear Regulatory Atlanta, Georgia 30303 Commission 12700 Hagers Ferry Road Elaine Wathen, Lead REP Planner Huntersville, North Carolina 28078 Division of Emergency Management 116 West Jones Street Mr. T. Richard Puryear Raleigh, North Carolina 27603-1335 Owner's Group (NCEMC)

Duke Power Company Mr. H. B. Barron 4800 Concord Road Vice President, McGuire Site York, South Carolina 29745 Duke Power Company 12700 Hagers Ferry Road Dr. John M. Barry Huntersville, North Carolina 28078 Mecklenberg County Department of Environmental Protection 700 N. Tryon Street Charlotte, North Carolina 28202

LIST OF PARTICIPANTS MEETING ON MCGUIRE 1996 UFSAR REVISION

.. MCGUIRE NUCLEAR PLANT. BUILDING 7438 JULY 9.1997 NAME AFFILIATION B. Travis MSE, Engineering Manager, McGuire H. Wallace Mod. Engineer Supervisor, McGuire M. Cash Manager, Regulatory Compliance, McGuire K. Crane - Regulatory Compliance, McGuire V. Nerses McGuire Senior Project Manager, NRC J. Nolin Reactor Coolant System Engineer, McGuire 1 R. Starr Mod. Engineer, McGuire '

R. Pierce CEN, McGuire P.T.Vu Regulatory Compliance, McGuire C. Ray Safety Analysis, Duke C. L. Naugle CM & TH, Duke D. Bortz Nuclear Design, Duke M. Sykes McGuire Resident inspector, Reg. ll R. Cross Regulatory Compliance, McGuire Enclosure 1

BC.QORD OF LICENSEE'S RESPONSE TO STAFF'S QUESTIONS RAISED IN JUNE 20.1997. MEETING NOTICE Section 1.4 Editoria!- updates organizational name changes.

Section 1.8.25.4 Editorial - corrects table number.

Section 1.8.26 Editorial- corrects error in radioactivity range covered by steamline radiation monitoring system. ,

Table 1-5 Editorial- needs effective dates printed on page and correction of other apparent errors.

Table 1-6. Daae 21 of 69 Editorial- corrects error in radioactivity range of monitor.

Table 1-6. Daaes 24 and 62 of 69 Editorial- corrects error in radioactivity range of monitor and corrects the method by which the monitors are powered.

Section 2.3 3 Editorial - update organizational changes.

Section 2.5.5.2 Editorial - correcte 1 a typographical error.

Section 3.4 Editorial correction is needed to make the information clear, Enclosure 2

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Section 3.6.2.2.1-Editorial - corrects information about Duke Design Specification availability.

Section 3.7.1.3 .

Incorporated NRC-approved information on Critical Damping Values used for the seismic design of Category 1 structures, systems, and components.

Section 3.7.2.1.3 Added an NRC-approved attemative analysis methodology to the McGuire system piping analysis described in FSAR.

-Table 3.20 Added arbitrary intermediate pipe break (per GL 87-11) Information to the Table.

Chapter 4 " List of Fioures" The deletion of Figure 4-22 and the addition of Figure 4-89 was to reflect the current design of the double encapsulated secondary source term.- The design change was evaluated per 10 CFR 50.59 Section 4.2.1.1.1.3-Updated to reflect the current analysis performed 'using TACO 3 methodQlogy. The- 1 methodology was approved by NRC in November 1989.

Section 4.2.1.2.2

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Updated to reflect the current bottom nozzle design used in the cores. The change was

evaluated in accordance with 10 CFR 50.59.

Section 4.2.1.3.1.1-Updated to reflect the current analysis performed using TACO 3 methodology. The.

methodology was approved by NRC in November 1989.

y Section 4.2.3.2.1' Updated the information in this section on reactivity control components to reflect tne current design. This change was done in accordance with 10 CFR 50.59.  :

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Sigpon 4.2.3.3.2 Editorial - Added words "and control rod wear" to be more cornplete in the information already presented.

Sectibn 4.3.:UiLI Recent power peaking uncertainty factors have been developed based on the CASMO-3/ TABLES-3/SIMULAT-3 methodology (see Topical Report DPC-NE-1004A) approved by NRC in letter dated April 26,1996. The uncertainties in this section were moved from the text and put into Table 4-22.

Section 4.3.2.6 Spent Pool Facility criticality analysis was revised to reflect Amendments 159 (Unit 1) 1 and 141 (Unit 2).

Sections 4.3.2.7.5 and 4.3.5 Editorial - rewritten for clarity and/or eliminated redundant information or information not pertinent.

Table 4-1 Correct an error in H2O to U ratios. The change was evaluated in accordance with 10 CFR 50.59.

Table 4-4. oaces 1 and 2

- Eliminate redundant information per 50.59 and increase the upper enrichment limit to coiraspond to new Technical Specification enrichment limit of 4.75% per license amendments '

159 (Unit 1) and 141 (Unit 2).

Table 4-4. Daae 3 Bumable poison rod clad outer material item was previously deleted and it should not have

. been deleted so it was reinstated.

- Table 4-5

-Changes to the reload cycle boron concentration made to be consistent with typical boron concentrations currently used in core designs. Change was done in acewdance with 10 CFR 50.59.

4 Table 4-6

- Reactivity requirementi for Rod Cluster Control Assemblies were changed, which wLs done in_ accordance with 10 CFR 50.59, to reflect typical values representative of current core designs.

Table 4-7 Results of critical benchmark experiments were changed to reflect the changes brought about by issuance _of license amendments 159 (Unit 1) and 141 (Unit 2).

Tables 4-8.4-914-10.4 Deleted because these tables contained critical benchmark information no longer used_in -

current criticality analysis methodology that was approved in license amendments-159 (Unit 1) and 141 (Unit 2).

Table 4-12 Licensee agreed that Table 4-13 was mistakenly repeated twice, it should also have been deleted from the May 1,1992, page that contained Table 4-14.

Table 4-22

In order to better document the uncertainties from different NRC approved methodologies,

- this Table was added.

Floures 4-22 and 4-89 Figure 4-22 was deleted because the secondary source configuration represented in this drawing will no longer be employed in fuNre core designs. Figure 4-89 is the configuration of -

the new secondary source design being u' sed. The evaluation for the new design was done in accordance with 10 CFR 50.59 by MCC-1553.26-00-0171 dated December 20,1995.-

Floure 4-30 The scanning process for figures will not permit the adding of the revision numbers at the location of the line where the change is; therefore, the revision numbers for such figures will indicate a change is made in the figure by the number being placeo, after scanning, at the bottom of the figure page.-

Fioure 4-34

. Typical Bumable Poison Rod arrangement was changed to correspond to the current arrangement. This change was done in accordance with 10 CFR 50.59.

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Fioure 4-51

-] Editorial- The maximum heat flui hot channel factor was changed in the legend from 1.50 to 1.00 at the 12-foot core height level to correspond with the graph.

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Section 5.2.2.3 Some words were added and deleted to provide more complete and accurate information.

,- The changes were made in accordance with 10 CFR 50.59.

s F Sections 5.5.13.2 and 5 5.13.3 b

Safety and relief valve design description and evaluation changes were made to provide more accurate information. These changes were made in accordance with 10 CFR 50.59

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(NSM-22333).

6- Table 5-10 This table of Reactor Coolant Pressure Settings had a few changes to reflect the information in the text. The changes were made in accordance with 10 CFR 50.59.

Table 5-31 Deleted all 16 pages of this table because the information was no longer current with NRC approved ISI plan.

Section 6.2.1.2.3 Licensee agrees that an editorial change of the current word " upstream" to " downstream" would be in order.

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Section 6.2.1.6.2

_ Editorial - added additional tests and inspections to the periodic inservice surveillance for ensuring the functional capability of the containment.

Table 6-49 thru 6-63 m

Editorial changes that were evaluated in accordtnce with 10 CFR 50.59.

Table 6-64 The replaced UFSAR page has Tables 6-63 and 6-64 on the same page. However, the new page only has Table 6-63. Table 6-64 was inadver'ently omitted so this needs to be corrected.

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. s Table 6-110 NRC copy in error.

Table 6-125 Notes in the Sequence of Operations injection to cold leg recirculation were clarified. The change was made in accordance with 10 CFR 50.59.

Section 7.6 4.1.1 Editorial. Th;s May 14,1996, revision to FSAR still contains an error.

Sections 7.6.8.1.3.1. 2 and 7.6.8.1.4 The Fuel Handling System refueling electricalinterlocks was totally rewritten. These changes were evaluated in accordance witn 10 CFR 50.59.

Section 7.6.11 1.9.2 This May 14,1996, revision to the FSAR has an editorial error.

Section 7.6.15.1.1 Unit 2 relocated the safety-related diesel generator tube oil system pressure switches and the FSAR was revised to describe the change since Unit 1 and Unit 2 are now different. The modification was evaluated in accordance with 10 CFR 50.59.

Section 7.7.1.12 Leose Parts Monitoring System (LPMS) was rewritten to reflect a new system that was instal;ed to replace the existing LPMS. This was evaluated in accordance with 10 CFR 50.59.

Section 7.7.13.2 In the FSAR writeup on the propagation of cable fires an exception is noted to the use of a fire retardant armored cable run through the Train B Switchgear Room. This change was done in accordance with 10 CFR 50.59. The May 14,1996, revision contained a typographical error in that the word " fines" was used instead of " fires."

Section 7,7.1.14.1 The controls section for the Fuel Handling Ventilation Exhaust System Instrumentation and Control was totally rewritten. This change was made as a result of redesign and it was evaluated in accordance with 10 CFR 50.59.

Section 7.7.1.15 and Floure 7-2Q This Section, " Acoustic Leak Detection System", was totally rewritten and it involved an NRC commitment change regarding the monitoring of the eight postulated break locations in the 10-inch cold leg accumulator injection piping. The change was done in accordance with 10 CFR 50.59.

Section 7.7.2.4 This Section pertains to ramp loading and unloading. Because of a Westinghouse change before initial startup of the plant, the equipment, although described in the FSAR, was never put into service. Therefore, the information on this non safety related equipment should never have been written up in the FSAR. This information was deleted from the FSAR since it did not correctly describe what was in the plant.

Table 7-14 Changos in the control room instrument auxiliary feedwater flow range evaluated in accordance with 10 CFR 50.59.

Fiaure 7-15 and Fiaure 7-19 Change in the Containment Pressure Control System eliminated the control on the H, skimmer. This was evaluated in accordance with 10 CFR 50.59.

Fiaures 7-10 and 7-11 NRC approved the elimination of the Upper Head injection System (UHIS). These Figures were deleted from FSAR because they were associated with the UHIS.

Tables 8-11. 8-12. and 8-13 These tables reflect the changes in the DC Auxiliary Control Power System that were evaluated in accordance with 10 CFR 50.59.

Fiaures 8-24 and 8-25 These figures reflect the changes in the phase fault stability analysis swing curves that were evaluated in accordance with 10 CFR 50.59.

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8 Floures 8-37. 8-38. and 8-39 These figures reflect the changes in the DC auxiliary power system, DC auxiliary control power system and vital instrumentation and control system battery duty cycles that were evalu,ated in accordance with 10 CFR 50.59.

4 Section 9.1 A number of subsections related to fuel storage and handling (both new fuel and spent fuel) were changed. These changes were evaluated in accordance with 10 CFR 50.59. '

Section 9 2.2 A number of subsections to he Nuclear Service Water System and Ultimate Heat' Sink were changed and/or totally rewritten. These actions were evaluated in accordance with 10 CFR 50.59.

Section 9 2 6 Changed to indicate that the Drinking Water System will now be supplied by the Chariotte i Municipal Utilities Department.. This change was evaluated in accordance with 10 CFR 50.59.

Section 9,2.8 3 As a result of the change of primary to secondary steam generator tube leakage limit as described in the licensee's letter dated October 1,1996, the 50 GPO limit in the er.isting FSAR was deleted.

Section 9.3.4

Clarified the system description of the Chemical and Volume Control System. .This change was evaluated in accordance with 10 CFR 50.59.-

Tables 9-1. 9-3. 9-4. 9-5. and 9-6 Changes to the fuel storage and handling system affected these associated Tables. The -

changes were evaluated in accordance with 10 CFR 50.59.-

Tables 9-8. 9-14. 9-15. 9-16. 9-17. 9-18.' and 9-19

- Tables were changed to reflect the 10 CFR 50.59 changes made to the FSAR text information on the Nuclear Service Water System and the Standby Nuclear Service Water

- Por d (SNSWP).

)

9 Table 9-28 Change evaluated in accordance with 10 CFR 50.59.

Floure 9-8 This figure was deleted because the licensee described in the text of the UFSAR the fuel storage regions' restriction as limited to assemblies meeting contain minimum required assembly bumups. These bumups are defined in the plant's Technical Specifications. This change was made in accordance with 10 CFR 50.59.  !

Floures 9-39. 9-40. and 9-41 '

These figures were modified to show heat transfer rates as part of the description for the heat load into the SNSWP. This change was evaluated in accordance with 10 CFR 50.59.

Floures 9-58. 9-59. 9-60. 9-61. 9-62. 9-63. 9-64. 9-93.

10-30.10-31.10-32.10-33.11-24. and 11-25 Licensee revised site drawings in the FSAR into summary one line flow diagrams without doing an evaluation in accordance with 10 CFR 50.59. It is not clear whether creating these summary diagrams of UFSAR drawings could be reducing informatiorvccmmitments.

Section 1M Procedure revisions in the Process and Effluent Radiological Monitoring Systems brought ,

about changes to the UFSAR. These changes were evaluated in accordance with 10 CFR 50.59.-

Table 11-22 Editorial - corrects some misaligned lines within the table.

Table 11-27 Deletes radiation detector EMF-32. This change was evaluated in accordance with 10 CFR 50.59.

Table 11-28 Editorial . while the licensee corrected some errors, other errors still persist. For example, detector number 2-EMF-36 (HH) is listed on page 2 of 4 with appropriate changes; however, 2 EMF-36 (HH) on page 3 of 4 is the same detector listed with different design service needs than the 2-EMF-36 (HH) on page 2 of 3.

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Section 13.4 ,

Editorial- rearranged paragraphs, eliminated typographical errors, and clarifed some of the text!

Section 15.1 The changes in the core power and reactor coolant transient write up was made consistent

- with the NRC approved Topical Report DPC-NE-3001-PA.

Section 15.2 and 15,4 The percentage of steam generator tubes plugged was increased to 18%. This and certain certain other changes were evaluated in accordance with 10 CFR 50.59, in addition, the updated physics parameters were made corssistent with the NRC approved Topical Report

- DPC-NE-3001-PA.

- Section 15.6 The write-up on the transition core was deleted since current cores now contain all Mark-BW fuel and the description of largs and small break LOCA and LOCA results are changed to be consistent with the NRC-approved Topical Report BAW-10168P-A and 10174.

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