ML20207L217

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Rev 1 to Sequoyah Element Rept, Pipe Support Design,Use of Snubber
ML20207L217
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 12/30/1986
From: Russell Gibbs
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20207K584 List:
References
221.10(B), 221.10(B)-R01, 221.10(B)-R1, NUDOCS 8701120023
Download: ML20207L217 (10)
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Text

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. o TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(B)

SPECIAL PROGRAM

( REPORT TYPE: SEQUOYAH ELEMENT REVISION NUMBER: 1 TITLE: PIPE SUPPORT DESIGN Use of Snubber PAGE 1 0F 9 REASON FOR REVISION:

1. To include TVA's corrective action plan information (see Section 10) and comply with current format.

PREPARATION b PREPARED BY:

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  • SRP Secretary's signature denotes SRP concurrences are in files, k APPROVED BY:

NIT \ O 'IOhCu n l,5) f'/k N/A N ECSP MANAGER DATE MANAGER OF HUCLEAR POWER DATE

(. CONCURRENCE (FINAL REPORT ONLY)

. TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(B)

SPECIAL PROGRAM REVISION NUM3ER: 1 PAGE 2 0F 9

1. CHARACTERIZATION OF ISSUE (S):

Concern: Issue:

SON-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."

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

Significant Condition Report #SCR SQN CEB 8615

3. DOCUMENT NOS.. TAG NOS., LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE IDENTIFICATIONS STATED IN ELEMENA Restraint on the vertical riser just outside reactor vessel (Units 1 and 2) of Upper Head Injection system.
4. INTERVIEW FILES REVIEWED:

Review of interview files for concern # SQN-86-001-02 shows the following information:

o NSRS ECP Review Sheet o Form A, ECTG M.1, Attachment F, Page 2 of 2 o Attachment B2, Standard Practice, Page 9 o Attachment B3, Standard Practice, Page 10 and 11

5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:

See Appendix A.

01900 - 12/09/86

, TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(B) i SPECIAL PROGRAM REVISION NUMBER: 1 I

PAGE 3 0F 9

6. WHAT 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. Reviewed design calculations to identify the types of I supports on the vertical risers of the Upper Head Injection System.
b. Reviewed as-constructed and/or as-designed pipe support l detail drawings to confirm the support types.

k.

9. DISCUSSION. FINDINGS. AND CONCLUSIONS:

Chronology:

o 03/86: lVA identities the discrepancy and reports the finding in the significant condition report 06/06/86: TVA receives the employee concern 08/86: TVA performs study calculation and demanstratas no failure or ihe systra 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 examiaed the supports on the vertical riser portion of the loop for both units (units #1 and

  1. 2).

(

, 01900 - 12/09/86 l

TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(B)

SPECIAL PROGRAM REVISION NUMBER: 1

('

PAGE 4 0F 9 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.
c. The load summary tables of the pipe supports were examined to confirm the support types used in the calculations.
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 point #44A is specified in the piping analysis problem #15-01

( (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 condition. The results of the TVA ana. lysis 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 tne seismic stress levels, and 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).

(

01900 - 12/09/86

TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(8)

SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 5 0F 9 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.

10. CORRECTIVE ACTION:

In its corrective action plan (CAP) (App. A, 5.s), TVA comniits to remove the snubber and install a rigid type support at this location before the restart of the plant. The evaluation team C. concurs with this CAP.

01900 - 12/09/86

, TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(8)

SPECIAL PROGRAM REVISION NUMBER: 1

(

PAGE 6 0F 9 APPENDIX A

5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
a. TVA, Sequoyah Nuclear Plant design isometric drawing 47K435-72, R0 of Problem 0600104-15-01, Unit #1
b. TVA, Sequoyah Nuclear Plant design isometric drawing 47K435-73, R0 of Problem 0600104-15-02, Unit #1
c. TVA, Sequoyah Nuclear Plant snubber design loads drawing 47B435-207, R1 of Problem 0600104 .3-01, Unit #1
d. TVA, Sequoyah Nuclear Plant snubber design loads drawing 478435-208, 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 478435-203, R1 of Problem 0600154-15-02, Unit #2
1. Pipe support detail drawings of the Problem 0600104-15-01, Unit #1:

pwa. # Rev. Dwn. # 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. Dwn. # 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 l-H45-80 1-H45-68

( 1 -H45-148 906 906 1 - H45-153 1 -H4 5-139 907 901 1-H45-69 902 903 01900 - 12/09/86

l

, TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(B) ,

SPECIAL PROGRAM ,

REVISION NUMBER: 1 PAGE 7 0F 9 APPENDIX A (cont'd)

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

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

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:

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

l 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

. J.(- 2-H45-130 906 2-H45-153 908 2-H45-139 901 2-H45-140 902

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
p. EDS piping analysis calculation 0600154-15-02, RS, Unit #2
q. TVA, Summary of Analysis of Problem 0600104-15-01, Rev. 7, Unit #1, RIMS access number 825-860716803
r. Sequoyah Nuclear Performance Plan, Volume II, R1, (07/14/86) l
s. TCA8 009, Corrective Action Plan (CAP) for the Element

'.21.10(8), (11/24/86)

6. WHAT REGULATIONS. LICENSING COMMITMENTS. DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA 7
a. Sequoyah Nuclear Plant rigorous analysis handbook bM e I

{

01900 - 12/09/86

\

  • TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(8) i SPECIAL PROGRAM l REVISION NUMBER: 1 V PAGE 8 0F 9 l

APPENDIX A (cont'd) l l

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 Bechtel to

( R. Anderson /M. Ali of TVA, (10/20/86)

1. RFI #SQN-647, (10/21/86) l (.,

i 01900 - 12/09/86

. TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.10(B)

SPECIAL PROGRAM REVISION NUM8ER: 1

(..

PAGE 9 0F 9 CATD LIST The following CATO identifies and provides corrective action for the findings included in this report:

22110 SQN 01 (11/20/86)

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  • REFERENCE - ECPS120J-ECPS121C TENNESSEE VALLEY AUTHORITY PAGE' - 98 ,

FREQUENCY - REQUEST OFFICE OF NUCLEAR POWER RUN TIME - 12:57:19

-) ONP - ISSS - RRM EMPLOYEE CONCERN PROGRAM '/ STEM (ECPS) RUN DATE - 12/02/86 LIST OF EMPLOYEE CONCERN I'.iddMATION CATEGORY: EN DES PROCESS & OUTPUT SUBCATEGORY: 22110 USE OF SNUBBER

) S GENERIC KEYHORD A H APPL QTC/NSRS' P KEYNORD B CONCERN SUB R PLT BBSH INVESTIGATION S CONCERN KEYHORD C NUMBER CAT CAT D LOC FLQB REPORT R DESCRIPTION KEYHORD D

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SQN-86-001-P02 EN 22110 N SQN NNNY SS. DURING THE EXIT INTERVIEW, THE CI ST K-FORM ATED THAT THE UPPER HEAD INJECTION S YSTEM VERTICAL RISER JUST GUTSIDE RE

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- ACTOR VESSEL (UNITS 1 AND 2) REQUIRE A RIGID SUPPORT, BUT INSTEAD A SHUB BER HAS USED.

) 1 CONCERNS FOR CATEGORY EN SUBCATEGORY 22110 3

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