ML20196F674
| ML20196F674 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/02/1988 |
| From: | Michael Ray TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8803040149 | |
| Download: ML20196F674 (7) | |
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4.
,A TENNESSEE VALLEN AUTHORITY CH ATTANOOGA, TENNESSEE 37401 SN 105B Lookout Place l
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l MAR 2 1988 l
U.S. Nuclear Regulatory Commission g
ATIN: Document Car. trol Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
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Docket Nos.
50-327 Tennessee Valley Authority
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50-328 SEQUOYAH NUCLEAR PLANT (SQN) - INTEGRATFD DESIGN INSPECTION (IDI) - NRC INSPECTION REPORT 50-327/87-48 and 50-328/87-48 provides TVA's supplemental response to IDI item D2.2-1. provides a list of ecmmittr9nts being made by TVA in thin submittal.
It is our understanding that the revised response prov'dod here!n t
completes TVA's actions on this item for unit 2 restart.
If you have any questions, please telephone D. L. Williar.s at (615) 632-7170.
Very truly yours, TENNESSEE VALLEY AllTHORITY i
M. J. R y, Deputy 1 rector Nuclear Licensing and Regulatory Affairs Enclosures cc:
Soo page 2 8803040149 880302 PDR ADOCK 05000327 0
DCD 1
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An Equal Opportt.nity Employer
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,o U.S. Nuclear Regulatory Commisolon h4AR 21988 i-Enclosures cc (Enclosures):
Mr. K. P. Barr, Acting Assistant Director for Inspection Programs TVA Projects Division U.S.' Nuclear Regulatory Commission Region II 101 Marietta Street, NW,' Suite 2900 Atlanta, Georgia 30323 Mr. C. C. Zech, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission Gne Whito Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Isou Ferry Road Soddy Daisy, Tennessee 37379 1
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,a ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT SUPPLEMENTAL RESPONSE TO IDI ISSUE D2.2-1 ITEM No.:
D2.2-1 TITLE: Design Pressure of ERCW System
SUMMARY
OF ITEM:
1.
Calculation B44 870326 006 is not conservativo in that it does not address the effect of components which may be isolated for maintenance.
2.
The calculation is also not conservative in that it does not use maximum flood levels in evaluating static head, nor does it discuss protection against overpressurization when the river level rises.above the normal maximum elevation of 683 feet.
2 The 150 lb/in g design pressure recommended in calculation B44 870326 3.
006 is inconsistent with the 160 lb/in2s value in Design Criteria SQN-DC-V-7.4, Revision 2.
4.
The governing code, ANSI B31.1-1967, does not allow throttling to reduce pressure without installing an overpressure relief volve.
CLASSIFICATION:
Documentation SUPPLEMENTAL RESPONSE:
In the December 29, 1987 responso to the NRC, TVA committed to "perform stress calculations to demonstrate that the EBR (Electric Board Room) and SBR (Shutdown Board Room) air-conditioners are not overstressed at the abnormal working pressures and obtain third-party verification of these calculations."
The strees analyses were documented in the following six calculation packages and were provided to Hartford Steam Boller Company (HSB) to perform a third party review:
CEB-CQS-345 R2 CEB-CQS-349 R1 CEB-CQS-347 R1 SCC-2E-CQS-408 SQN-67-D053. R0 SQN-67-D053, RO.
During the review, a discrepancy was discovered within ASME Code Section VIII in the area of allowable bending stresses for cast iron flanges. Telephone conversations among TVA, HSB, and knowledgeable members of the ASME Subcommittee on Pressure Vessols confirmed the discrepancy.
Subcommittee personnel identified the correct requirements, whereupon TVA incorporated the information into the calculations, and HSB reviewed them. Their approval is documented in the attached letter.
HSB comments have been incorporated into l
the six calculation packages.
As a post-restart action, TVA will initiate a formal ASME Code inquiry requesting that the Section VIII discrepancy be corrected.
G
02/26/1998 14:52
- F M, FAX UF-400 ****
06701053 P.02
- e' 9e Attachmsnt 0226 003 l
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February 22,1988 1
To R.
E.
Daniels, Lead Mechanical Engineer, Sequoyah Nuclear Plant Subjects Results of Third Party Review of Calculations which Address a Design Pressure Increase in the EBR and GBR A/C Condensers and Oil Coolers Re:
829
'88 0202 002 Memorandum'fhom R.,
E.
Daniels to E.
L.
Farrow Dated 2/2/88 l
Re B29 ' 88 0219 002 Memorandum from R.
E.
Daniels to l
i E.
L.
Farrow Dated 2/19/88 This report documents the findings of a technical review of six calculations addressing an' Essential Raw Cooling Water (ERCW) i pressure increase of 150 psi to 155 pot.
in the Eloctric Board Room (EBR) and shutdown Doard Room (SBR) air conditioning condon-s'e r u and oil cool. ors.
This work was requested in the reference memorandums indicated above.
The memos instruct Hart ford Steam Boiler Inspection and Insurance Co. (HSB) to provide third party verification of the calculations with respect to the various codes used in the calculations.
The design code involved is the ABME Boiler and Pressure Vessel Code section VIII, Div 1.
The ' goal of the review was to verify the technical accuracy of the calculations, and see that all code stress allowables are met.
We did not perform a detailed QA of the calculations.
For j
- example, we did not indopendently verify the accuracy of the design inputs provided by TVA.
Eight vessels, four condensers and four oil coolers, make up the equipment analyzed for the 5.
psi pressure incresce. The EDR and SBR each cont'ain two separatn A/C units identified as AA and BB.
1 Below are listed the six calculations checked in the review.
j 1
The Hartford steam nouer ImFolon ad lmunnce Co.
l Osw Sute stno l
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02/26/1953 14:53
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- F At # AX tf-400 ****
C6701053 P.04 s:.
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i QQUQLWQlDUE The six calculations referenced above were checked for their numerical
- accuracy, and interpretation and use of code design equations and stress allowables.
Whenever possible the design input was checked against the indicated references.
The calcula-tions properly considered all of the major components in the condonsors and oil coolers for the abnormal pressure increase of 5.
psi.
During the review, HSD brought to TVA's attention that Section VIII.Div.
1 Appendix 2 apparently prohibits an increase to 1.5S for bending stresses in cast iron flanges.
A review of section VIII, Div. 1 revealed that the Code is inconsistent in its treat-ment of bending allowables.. Telephone conversations with members of the Subcommittee on pressuro Vasemis knowledgable in the design rules confirmed that there is an apparent error in the bending limit for cast iron.
Confirmation was received that this issue would be addressed at the next committee meeting.
In additon TVA will initiate a formal inquiry requesting correction d
of the Code.
Under the abnormal pressure conditions all of the cast iron flanges are acceptable usinD a stress allowable of 1.59
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for bending.
In conclusion, the strens calculations reviewed comply with the relevant requirements of AEME Code Baction
- VIII, Div.
1 and support the 5 psi pressure increase for the postulated abnormal condition.
fb P PA k.
Thomas P'.
Pastor P.E.
Senior Engineer
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R.
M.
Vogel Project Engineer Hartford Steam Boiler Inspection & Insurance Co.
j Code Support Services Division Engineering / Claim Department One State St.
Hartford, Ct. 06102 e
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02/26/1953 14253 ococ PM, FAX (F-400 *co 06701053 P.03
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Calculation CEB-COS-345 R2 Title Qualification of 20 in.
Dat.es 1/31/88 Condenser Head-Return Codes Used -
1974 ASME B & PV Code,Section VIII, Div i 2.
Calculation #
CEB-COS-349 Rt.
Title Flange Design for Condenser
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Inlet Head Date 1/31/88 i
Codes Used:
1974 ASME B & PV Code Section VIII,Div 1 3.
Calculation #: CEB-COS-347 R1
Title:
Evaluation of Condenser Oil Cooler for a change Design Aressure in from 150 psi to 180 psi.
Date 1/31/88 Design Code used: 1974 ASME B&PV Code,Section VIII, Div i 4.
Calculation #
SCO-2E-COS-408 Title Qualification of Shutdown Board Room 011
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Date Cooler Heads 2/8/88 Design Code usedt1974 ASME B & PV Code,Section VIII, Div.1 5.
Calculation #3 SON-67-D053 Ro e
Title e
EBR Air Conditioning Unit Condenser and Oil cooler Analysis Date: 2/1/88 Code's used 1985 ASME B & PV Code,Section VIII, Div 1 6.. Calculation #3 SON-67-DOS 3 R0 Title BBR Air Conditioning Unit Condenser Analysis Oil ' Cooler Date: 2/4/88 Codes used:
1986 ASME B & PV Code,Section VIII, Div.
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it 2
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- e; ENCI.0SURE 2 SEQUOYAH NUCLEAR Pl. ANT LIST OF COMMITMENTS p_2.2-1 Af ter SQN unit 2 restart, TVA will initiate a _ formal ASME Code inquiry requesting that.the Section VIII discrepancy be corrected.
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