L-MT-06-028, Calculation CA-04-042, Rev 0, MNGP AST - Post LOCA Ph Analysis.
| ML061310448 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 09/06/2005 |
| From: | - No Known Affiliation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 3494, L-MT-06-028 CA-04-042, Rev 0 | |
| Download: ML061310448 (12) | |
Text
MONTICELLO NUCLEAR GENERATING PLANT 3494 TITLE: CALCULATION COVER SHEET Revision 15 Page 1 of 4 CALCULATION COVER SHEET Page 1 of Title MNGP AST - Post LOCA pH Analysis CA 042 Add. 0 PART A - (Not Applicable to Vendor Calcs)
Assigned Personnel Name (Print) Signature Title Initials Record of Issues Total Last Approval Rev Description Sheets Sheet Preparer Verifier Approval Date Verification Method(s)
Review Alternate Calculation Test Other Technical Review (per 4 AWI-05.08.07 (FP-E-MOD-07))
3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: ______________________________________
FOR ADMINISTRATIVE Resp Supv: CNSTP Assoc Ref: 4 AWI-05.01.25 SR: N Freq: 0 yrs USE ONLY ARMS: 3494 Doc Type: 3042 Admin initials: Date:
Approved (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3494 TITLE: I CALCULATION COVER SHEET Revision 15 Page 2 of CA 042 PART B - (Applicable to Vendor Calculations Only)
Sargent &
Vendor Name Lundy Vendor Calc No: 2004-02105 R l Vendor Approval Date: 8/31/05 IXI Form 3345 or QF-0547 attached.
Safety related? If safety related, attach DIA or See Other Comments Reviewed by: Joel Beres / Mike Aleksey 2&&66&
Print Name Date Accepted by: Dennis Zercher ) Zar, r Print Name Eng. w i g n a t u r e Date Record of Issues Revision Description Total No. of Sheets Last Sheet Number 0 Original Issue PART C - Design Basis Data (Complete for all Calculations) 10 CFR50.59 Screening or Evaluation No: N/A Associated Reference(s): AST LAR Does this calculation: YES NO Calc No(s), Rev(s), Add(s)
GENE-B2 1000594-1-R2, "Radiological Analyses of Design Basis Accidents - Task 24': Section 3.1 only.
Supercede another calculation? See comments.
Augment (credited by) another calculation? IXI Derive inputs from another calculation? ' CA 190 R 1 Add. 0; CA-04-036 R 1 Add. 0; CA 037 R2 Add. 0; CA-04-210 RO Add. 0 Affect the Fire Protection IXI If Yes, attach Form 3765 Program per Form 3765?
Affect piping or supports? If Yes, attach Form 3544 Approved (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3494 TITLE: CALCULATION COVER SHEET Revision 15 Page 3 of 4 Affect IST Program Valve or If Yes, inform IST Coordinator and provide copy of Pump Reference Values, and/or calculation Acceptance Criteria?
Page 3 of CA 042 List all documents/procedures that are based on this calculation (include revision):
USAR, Rev 21 (Section 14.7 and associated tables)
List all plant procedures used to ensure inputs/assumptions/outputs are maintained (include revision):
0089 Rev 17, 0086 Rev 28. Also see Future Needs below.
What Systems or components are affected?
System Code(s) (See Form 3805): SLC, CS Component IDs (CHAMPS Equip): N/A DBD Section (if any): B.3.5, B.3.1 Topic Code (See Form 3805): DBAE Structure Code (See Form 3805): N/A Other Comments: Sargent & Lundy calculation 2004-02103 Rev 1 incorporates AAC Calculation #MNGP-005 Rev 1 (see attachment for cross-references).
Note: This calculation is not incorporated as part of MNGP's design basis until the associated LARs are approved (AST Phase 1 and 2).
Future needs: Update relevant USAR relevant sections and other plant documents in accordance with the MNGP AST Implementation Plan (OTH027344).
Approved (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3494 TITLE: CALCULATION COVER SHEET Revision 15 Page 4 of 4 This calculation was completed in accordance with the approved project work plan (DIA Equivalent) for the AST Implementation S&L Letter #SLMON-2003-085, and PO38317.
Approved (Signatures available in Master File)
Attachment to Form 3494, CA-04-042 Rev 0 Page 1 of 1 MNGP AST Project Calculations List Calculation No. Title
[Applied Analysis Corporation (AAC) performed DBA calculations for the AST project. Sargent & Lundy provided independent verification and documented results in S&L calculations which incorporated the AAC calculations as attachments. The S&L calculations were accepted by MNGP via the vendor calculation control process (4 AWI-05.01.25). Thus MNGP # each DBA calculation has three numbers - MNGP, S&L, and AAC.
S&L #
AAC calculations will reference other AST calculations by their AAC AAC # number. This list is provided for proper cross-reference of calculations.]
03-190 Design Inputs For Alternate Source Term (AST) Radiological N/A Analysis N/A 04-036 MNGP AST - Offsite Post-Accident Atmospheric Dispersion 2004-01852 Analysis MNGP-001 04-037 MNGP AST - CR/TSC Post-Accident Atmospheric Dispersion 2004-02100 Analysis MNGP-002 04-038 MNGP AST - LOCA Radiological Consequence Analysis 2004-02101 MNGP-003 04-039 MNGP AST - MSLBA Radiological Consequence Analysis 2004-02102 MNGP-004 04-040 MNGP AST - CRDA Radiological Consequence Analysis 2004-02103 MNGP-005 04-041 MNGP AST - FHA Radiological Consequence Analysis 2004-02104 MNGP-006 04-042 MNGP AST - Post-LOCA pH Analysis 2004-02105 MNGP-007 04-210 Alternative Source Term - Core Isotopic Inventory 2004-07600 N/A 05-130 Post LOCA Direct Dose to the Control Room From External 2005-00480 Sources N/A 05-134 Post-LOCA Steam Pipe Internal Temperature 30-Day Profile for 2005-06343 Radiological Dose Analysis MNGP-012
MONTICELLO NUCLEAR GENERATING PLANT 3345 TITLE: VENDOR CALCULATION REVIEW CHECKLIST Revision 3 Page 1 of 1 C A - 04 - 042, Rev 0 The purpose of the review is to ensure that the vendor calculation or analysis complies with the conditions of the purchase order and is appropriate for its intended use. The purpose of the review is not to serve as an independent verification. Independent verification of the calculation or analysis by the vendor should be evident in the document.
The reviewer should use the criteria below as a guide to assess the overall quality, completeness and usefulness of the calculation or analysis. The reviewer is not required to check the vendor's calculations in detail.
See 4 Awl-05.01.25 (CALCULATIONIANALYSIS CONTROL) for guidance. Place initials by items reviewed.
REVIEW Form 3544 (PIPING AND SUPPORT NUMBERING) completed for calculations affecting piping or supports.
Design inputs correspond to those which were transmitted to the vendor.
Assumptions are described and reasonable. Basis for assumptions identified.
Applicable codes, standards and regulations are identified and met.
I Applicable construction and operating experience is considered.
Applicable structure(s), system(s), and component(s) are listed.
Formulas and equations documented and unusual symbols are defined.
Acceptance criteria are identified, adequate and satisfied.
Results are reasonable compared to inputs.
Source documents are referenced.
The calculation is appropriate for its intended use.
The calculation complies with the terms of the Purchase Order.
Inputs, assumptions, outputs, etc. which could affect plant operation are enforced oodf eG.
by adequate rocedural controls. List any affected procedures.
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Completed By: Date: '%/wV6/&
Approved (Signatures available in Master File)
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ISSUE
SUMMARY
Form SOP-0402-07, Revision 7 PROJECT NAME:
PROJECT NO.: 11163-013 NUCLEAR SAFETY- RELATED 2004-02105 NOT NUCLEAR SAFETY-RELATED MNGP AST - Post-LOCA pH Analysis EQUIPMENT NO.:
DATE FOR REV.: 04/15/04 PREPARER W. J. Johnson/(See original for signatures) DATE: 04115/04 REVIEWER R. Kahn/(See original for signatures) DATE: 04115/04 APPROVER M. A. Pressburger/(See original for signatures) DATE: 04/15/04 pages), Attachment B - List of Electronic Files (1 page)
INPUTS/ ASSUMPTIONS DATE FOR REV.:
INPUTS/ ASSUMPTIONS DATE FOR REV.:
NOTE: PRINT AND SIGN IN THE SIGNATURE AREAS SOP040207.DOC Page 1 of 1 Rev. Date: 04/08/2005
Calcs. For MNGP-AST - Post-LOCA pH Analysis Calc No. 2004-02105 Rev. 1 Date X Safety Related Non-Safety Related Page 2 of 5 Client Nuclear Management Company Prepared by Date Project Monticello Nuclear Generating Plant Reviewed by Date Proj. No 11163-013 Equip. No. Approved by Date TABLE OF CONTENTS Page 1 PURPOSE AND SCOPE ...................................................................................................................3 2 DESIGN INPUT.................................................................................................................................3 3 ASSUMPTIONS ................................................................................................................................3 4 METHODOLOGY AND ACCEPTANCE CRITERIA.....................................................................3 5 CALCULATIONS .............................................................................................................................4 6 RESULTS AND CONCLUSIONS ....................................................................................................4 7 REFERENCES...................................................................................................................................5 ATTACHMENT A. Calculation No. MNGP-007, MNGP AST - Post-LOCA pH Analysis (38 pages)
....................................................................................................................................................... A-1 ATTACHMENT B. Computer File Listing For Calculation No. MNGP-007 (1 page) ....................B-1 File GQ308-2.DOC Form GQ-3.08.1 Rev.2
Calcs. For MNGP-AST - Post-LOCA pH Analysis Calc No. 2004-02105 Rev. 1 Date X Safety Related Non-Safety Related Page 3 of 5 Client Nuclear Management Company Prepared by Date Project Monticello Nuclear Generating Plant Reviewed by Date Proj. No 11163-013 Equip. No. Approved by Date 1 PURPOSE AND SCOPE A new calculation has been prepared to demonstrate that, in the event of a Loss-of-Coolant Accident (LOCA) at Nuclear Management Companys (NMC) Monticello Nuclear Generating Plant (MNGP), the pH of the Torus Suppression Pool remains above 7.0, thus ensuring that the particulate iodine deposited in the suppression pool does not re-evolve and become airborne as elemental iodine. The calculation is documented in Applied Analysis Corp. (AAC) calculation MNGP-007 (Reference 1), which is included in its entirety in Attachments A and B. This analysis was performed in accordance with the guidance provided in Regulatory Guide 1.183 (Reference 2).
The purpose of this calculation is to document the S&L independent verification of AAC calculation MNGP-007. The verification consists of a review to assure that the methodology used in the calculation is appropriate to the purpose of the calculation, that the inputs are in accordance with the approved inputs provided by NMC, and that the results of the analysis are consistent with the inputs and methodology.
2 DESIGN INPUT The design inputs and their bases are identified in Section 4.0 of MNGP-007 (Attachment A). MNGP specific inputs used in the pH calculation are referenced to NMC Design Input Request (DIR) calculation CA-03-190 (Reference 3). Additional inputs are obtained from published documents. The design inputs are therefore approved by NMC.
3 ASSUMPTIONS The assumptions used in the determination of the suppression pool pH are documented in Section 3.0 of MNGP-007 (Attachment A). These assumptions are consistent with the methodology and data used in the calculation. Furthermore, these assumptions are consistent with NMC input per calculation CA 190 (Reference 3).
4 METHODOLOGY AND ACCEPTANCE CRITERIA Methodology Calculation MNGP-007 follows the methodology developed by the NRC in NUREG/CR-5950 (Reference 4). The calculation considers the effects on pH of cesium hydroxide production due to cesium releases from the core, hydroiodic acid production due to iodine releases from the core, hydrochloric acid production due to radiolysis of chloride-bearing cable and nitric acid produced by irradiation of water and air. The effect of carbonic acid due to the absorption of carbon dioxide in the suppression pool water is conservatively bounded by selecting the lowest initial pH for the suppression File GQ308-2.DOC Form GQ-3.08.1 Rev.2
Calcs. For MNGP-AST - Post-LOCA pH Analysis Calc No. 2004-02105 Rev. 1 Date X Safety Related Non-Safety Related Page 4 of 5 Client Nuclear Management Company Prepared by Date Project Monticello Nuclear Generating Plant Reviewed by Date Proj. No 11163-013 Equip. No. Approved by Date pool water. The effect of injecting sodium pentaborate from the standby liquid control system (SLCS) is also evaluated. Although the time dependent release of material from the core is used consistent with the assumptions in the LOCA analysis from Regulatory Guide 1.183, the radiation exposure is the same as used for equipment qualification. This is conservative since the equipment qualification doses are based on instantaneous releases. These effects and the method of evaluation used in MNGP-007 are consistent with Reference 4 and with similar analyses approved by the NRC for other plants. The methodology is therefore considered appropriate and conservative.
Acceptance Criteria Appendix A of Regulatory Guide 1.183 indicates that iodine re-evolution should be considered for suppression pool pH values less than 7. Therefore the acceptance criterion for this calculation is that the long term suppression pool pH value remain above 7 for the duration of the accident.
5 CALCULATIONS Not applicable to this calculation.
6 RESULTS AND CONCLUSIONS The time results of the suppression pool pH studies are summarized in Section 7.0 of MNGP-007 (Attachment A). Two cases are considered. The first case does not utilize the SLCS for pH control, and the pH is well below the acceptance value of 7.0. This implies the SLCS will be required to assure the suppression pool pH remains above 7.0. The second case demonstrates that utilizing the SLCS results in a final suppression pool pH of 8.59, which is well above the acceptance value of 7.0.
Note that the case that utilizes the SLCS starts the pH calculation at 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the start of the accident, which is the time at which it is assumed SLCS injection is complete. Prior to this time, sump pH is not considered critical because the behavior of iodine in the containment is governed by thermal-hydraulic conditions and is not affected by re-evolution. It should also be noted that a sensitivity study was performed that demonstrated that the pH results of the SLCS case are not very sensitive to the amount of cable in the drywell.
Based on the above discussion, it is concluded that the methodology used in the MNGP-007 is appropriate to the purpose of the calculation, that the inputs are in accordance with the approved inputs provided by NMC, and that the results of the analysis are consistent with the inputs and methodology.
File GQ308-2.DOC Form GQ-3.08.1 Rev.2
Calcs. For MNGP-AST - Post-LOCA pH Analysis Calc No. 2004-02105 Rev. 1 Date X Safety Related Non-Safety Related Page 5 of 5 Client Nuclear Management Company Prepared by Date Project Monticello Nuclear Generating Plant Reviewed by Date Proj. No 11163-013 Equip. No. Approved by Date 7 REFERENCES
- 1. MNGP-007, Revision 1, MNGP AST - Post-LOCA pH Analysis, prepared by Applied Analysis Corp. for Nuclear Management Company, Monticello Nuclear Generating Plant
- 2. Regulatory Guide 1.183, Alternative Radiological Source Term for Evaluating Design Basis Accidents at Nuclear Power Plants, Revision 0, USNRC, July 2000
- 3. NMC Calculation CA-03-190, Design Inputs for Alternate Source Term (AST) Radiological Analysis, Revision 1
- 4. NUREG/CR-5950, Iodine Evolution and pH Control, USNRC, December 1992 (Final Page)
File GQ308-2.DOC Form GQ-3.08.1 Rev.2
Calcs. For MNGP-AST - Post-LOCA pH Analysis Calc No. 2004-02105 Rev. 1 Date X Safety Related Non-Safety Related Page B-1 of B-1 Client Nuclear Management Company Prepared by Date Project Monticello Nuclear Generating Plant Reviewed by Date Proj. No 11163-013 Equip. No. Approved by Date ATTACHMENT B. Computer File Listing For Calculation No. MNGP-007 Associated with AAC calculation No. MNGP-007 are a number of files, including Excel spreadsheet files that contain input data and calculate results. All of the files identified in MNGP-007 are contained on a compact disk (CD) associated with this calculation. The list of files and the purpose of each file is summarized in the list below.
File Name Purpose MNGP-007\
DVCS_MNGP_007.pdf Design Verification Comment Sheet MNGP_007_Coversheet.pdf Signed Coversheet DVCS_MNGP_007R1.pdf Design Verification Comment Sheet, Revision 1 MNGP_007_R1_Coversheet.pdf Signed Coversheet, Revision 1 30 Day Beta Dose CF.xls Spreadsheet for determination of Drywell Beta dose 30 Day Gamma Dose.xls Spreadsheet for determination of Drywell Gamma dose Cs-Halogen Mass Inventory Spreadsheet for determination of Br/Cs/I mass inventory Determination.xls Drywell Cable Surface Area Spreadsheet with the data for cable surface area determination Determination.xls Eagle-Picher Sodium Pentaborate Data Pentaborate data sheet Sheet.pdf SP pH With CsOH - No SLCS.xls Spreadsheet for pH analysis without Sodium Pentaborate SP pH With SLCS - No CsOH.xls Spreadsheet for pH analysis with Sodium Pentaborate (Final Page)
File GQ308-2.DOC Form GQ-3.08.1 Rev.2