ML20214U886

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Rev 0 to TVA Employee Concerns Special Program:Pipe Support Design
ML20214U886
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 11/01/1986
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20214T770 List:
References
221.10-(B), 221.10-(B)-R, 221.10-(B)-R00, NUDOCS 8612090438
Download: ML20214U886 (8)
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. TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(B)

SPECIAL PROGRAM REPORT TYPE: SEQUOYAH ELEMENT REVISION NUMBER: 0 TITLE: PIPE SUPPORT DESIGN Use of Snubber PAGE 1 0F 8 REASON FOR REVISION:

PREPARATION PREPARED BY:

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ECSP MANAGER DATE MANAGER OF HUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY)

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TVA ENPLOYEE CONCERNS REPORT NUM8ER: 221.10(8)

SPECIAL PROGRAM REVISION NUMBER: O PAGE 2 0F 8 1

l. CHARACTERIZATION OF ISSUE (S):

Concern: Issue:

SQN-86-001-02 Upper head injection system vertical "During the exit interview, riser has a snubber type support the CI stated that the Upper instead of a rigid type support as Head Injection System vertical required, riser just outside reactor vessel (Units 1 and 2) require '

a rigid support, but instead a snubber was used."

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2. HAVE ISSUES BEEN IDENTIFIED IN ANOTHER SYSTEMATIC ANALYSIS? YES X NO Identified by TVA Date 03/06/86 Documentation Identifiers:

Significant Condition Report #SCR SQN CEB 8615

3. DOCUMENT NOS., TAG N05.. LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE IDENTIFICATIONS STATED IN ELEMENT:

Restraint on the vertical riser just outside reactor vessel

! (Units 1 and 2) of Upper Head Injection system.

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4. INTERVIEW FILES REVIEWFD:

Review of interview file for employee concern #SQN-86-001-02 shows no additional information other than "K" form and generic applicability sheet (App. A, 7.f).

5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:

See Appendix A.

4 i

01900 - October 27, 1986 i - .

, TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(B)

SPECIAL PROGRAM REVISION NUMBER: 0

/

PAGE 3 0F 8

6. WHIT REGULATIONS. LICENSING COMMITMENTS. DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA?

See Appendix A.

7. LIST REQUESTS FOR INFORMATION. MEETINGS. TELEPHONE CALLS. AND OTHER DISCUSSIONS RELATED TO ELEMENT.

See Appendix A. -

8. EVALUATION PROCESS:
a. Review design calculations to identify the types of supports on the vertical risers of the Upper Head Injection System.
b. Review as-constructed and/or as-designed pipe support detail drawings to confirm the support types.
c. Evaluate findings.
9. DISCUSSION. FINDINGS. AND CONCLUSIONS:

Discussion:

At the Sequoyah nuclear plant, the upper head injection piping system extending from the containment penetration to the reactor vessel head consists of two similar loops per unit. Each loop contains four vertical risers in the vicinity of the reactor vessel. A total of 13 rigid and snubber type supports are located on these four risers. The evaluation team examined the supports on the vertical riser portion of the loop for both units (units #1 and

  1. 2).

The review was performed as follows:

a. A list of rigid and snubber type supports located on the vertical risers was prepared based on the design isometric drawings. This list contained a total of 52 supports (13 for each set of four risers on each of the two loops of each unit).
b. The input data of the piping analysis problems were reviewed to verify the types of supports specified in the

! calculations. This required review of four piping analyses.

01900 - October 27, 1986

TVA EMPLOYEE CONCERNS REPORT NUM8ER: 221.10(B)

SPECIAL PROGRAM REVISION NUMBER: 0 f

+

PAGE 4 0F 8

c. The load summary tables of the pipe supports were examined to confirm the support types used in the calculations.

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d. As-constructed and/or as-designed pipe support detail drawings were reviewed to verify agreement between them and as-analyzed support types.

The results of the review show that a rigid type support at node L point #44A is specified in the piping analysis problem #15-01 l

(Units #1 and #2), while as-constructed support detail drawings (1-H45-9, Rev. 2 and 2-H45-9, Rev. 2) identify a snubber type support at this location. In March 1986, this discrepancy was identified by TVA in a significant condition report SCR SQN CEB 8615 (Section 2.0). On August 24, 1986, TVA performed a study calculation for the analysis problem #15-01 specifying a snubber type support at node point #44A to reflect the as-constructed L condition. The results of the TVA analysis demonstrate that no ,

failure of the Upper Head Injection System will result from this ,

deficiency (App. A, 7.h). The evaluation team agrees with TVA's conclusion since the change from a rigid type support to a snubber type support will have no impact on the seismic stress levels, and

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the thermal stress levels will be generally lower due to the added flexibility of the system.

Irrespective of the study calculation results TVA is discussing replacement of the installed snubber type support with the rigid type support before the restart of SQN Unit #2 (App. A, 7.h and 7.1).

Findings _:

A snubber type support instead of the rigid type support shown on the drawing exists on the vertical riser of the Upper Head Injection System on both units. This has also been identified in TVA's report SCR SQN CEB 8615.

Conclusion:

The concern, that a snubber type support has been used on one riser per unit where a rigid type support is specified in the analysis, is valid. TVA has options of formally finalizing calculations to substantiate snubber installation or of replacing the snubber with a rigid support. j 2

01900 - October 27, 1986

TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(B)

SPECIAL PROGRAM REVISION NUMBER: 0 PAGE 5 0F 8 APPENDIX A

5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
a. TVA, Sequoyah Nuclear Plant design isometric drawing 47K435-72, RO of Problem 0600104-15-01, Unit #1
b. 1VA, Sequoyah Nuclear Plant design isometric drawing 47K435-73, RO of Problem 0600104-15-02, Unit #1
c. TVA, Sequoyah Nuclear Plant snubber desig'n loads drawing 478435-207, R1 of Problem 0600104-15-01, Unit #1
d. TVA, Sequoyah Nuclear Plant snubber design loads drawing 47B435-208, R1 of Problem 0600104-15-02, Unit #1
e. TVA, Sequoyah Nuclear Plant, EDS design isometric drawing 0600152-15-01, Rev. 908 of Unit #2 (01/30/76)
f. TVA, Sequoyah Nuclear Plant, EDS design isometric drawing 0600152-15-02, Rev. 909 of Unit #2 (01/30/76)
g. TVA, Sequoyah Nuclear Plant snubber design loads drawing 478435-202, R1 of Problem 0600154-15-01, Unit #2
h. TVA, Sequoyah Nuclear Plant snubber design loads drawing 47B435-203, R1 of Problem 0600154-15-02, Unit #2
1. Pipe support detail drawings of the Problem 0600104-15-01, Unit #1:

Dwg d Rev. Dwa. # Rev. Dwa. # Rev.

1-H45-18 906 1-H45-41 908 1-H45-32 902 1-H45-19 909 1-H45-42 908 1-H45-33 902 1-H45-22 907 1-H45-45 908 1-H45-9 2 1-H45-23 907 1-H45-46 906 1 -H45-10 902 1-H45-11 902

j. Pipe support detail drawings of the problem 0600104-15-02, Unit #1:

Dwa. # Rev. Dwa. # Rev. Dwa. # Rev.

1-H45-76 908 1-H45-149 908 1-H45-140 1 1 -H45-77 906 1-H45-152 907 1-H45-67 902 1-H45-80 906 1-H45-153 907 1-H45-68 902 1-H45-148 906 1-H45-139 901 1-H45-69 903 01900 - October 27, 1906

TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(B)

SPECIAL PROGRAM REVISION NUMBER: 0 1

PAGE 6 0F 8 APPENDIX A (cont'd)

k. Pipe support detail drawings of the problem 0600154-15-01, Unit #2:

Rev. Dwn. # Rev. Dwn. # Rev.

Dwa. 1 2-H45-18 3 2-H45-41 908 2-H45-9 2 2-H45-19 904 2-H45-42 908 2-H45-10 2 2-H45-22 905 2-H45-45 907 2-H45-11 1 2-H45-23 3 2-H45-46 910 2-H45-32 1 2-H45-33 1

1. Pipe support detail drawings of the problem 0600154-15-02, Unit #2:

2-H45-76 908 2-H45-148 908 2-H45-67 1 2-H45-77 906 2-H45-149 909 2-H45-68 3 2-H45-80 908 2-H45-152 908 2-H45-69 906 2-H45-130 906 2-H45-153 908 2-H45-139 901 2-H45-140 902 i

i m. EDS piping analysis calculation 0600104-15-01, R6, Unit #1

! n. EDS piping analysis calculation 0600104-15-02, RS, Unit #1

< o. EDS piping analysis calculation 0600154-15-01, RS, Unit #2 1

p. EDS piping analysis calculation 0600154-15-02, RS, Unit #2 i
q. TVA, Summary of Analysis of Problem 0600104-15-01, Rev. 7 Unit #1, RIMS access number 825-860716803
r. Sequoyah Nuclear Performance Plan - Draft of Volume II, R1, (07/14/86)
6. WHAT REGULATIONS. LICENSING COMMITMENTS. DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA 7 ,

i a. Sequoyah Nuclear Plant rigorous analysis handbook

b. TVA, Sequoyah Nuclear Plant pipe support design manual (PSDM), Volume III 01900 - October 27, 1986

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TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(B)

SPECIAL PROGRAM REVISION NUMBER: 0 PAGE 7 0F 8

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APPENDIX A (cont'd)

7. LIST REQUESTS FOR INFORMATION. MEETINGS. TELEPHONE CALLS. AND OTHER DISCUSSIONS RELATED TO ELEMENT:
a. RFI #SQN - 510,(08/27/86)
b. RFI #SQN - 511,(08/27/86)
c. RFI #SQN - 618, (10/04/86) ,
d. RFI #SQN - 625,(10/08/86)
e. Telephone call from S. Chitnis, Bechtel, to G. McNutt, TVA, (08/26/86)
f. RFI #SQN-640, (10/16/86)
g. RFI #SQN-642, (10/16/86)
h. Telephone call from D. Mohanty of 8echtel to R. Anderson /M. Ali of TVA, (10/20/86)
1. RFI #SQN-647, (10/21/86) 01900 - October 27, 1986 L

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