ML18044A408
| ML18044A408 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 12/11/1979 |
| From: | Huston R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-79-02, IEB-79-2, NUDOCS 8001110159 | |
| Download: ML18044A408 (12) | |
Text
'*
I. *~.
consumers Power company General Offlc*: 212 Wat Mlchlpn Avenu*: Jeckson, Michigan 49201 * (617) 788-0660 December 11, i979 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT DAY RESPONSE TO IE BULLETIN 79-02, REV 2 -
"PIPE SUPPORT BASE PLATE AND EXPANSION ANCHOR EVALUATION" Enclosed please find Consumers Power Company's 30-day response to IE Bulletin 79-02, Rev 2 (Pipe Suppdrt Base Plate and Expansion Anchor Evaluation).
This response is in compliance with Item 8 of IE Bulletin 79-02, Rev 2.
A final report for the Pipe Support Base Plate and Expansion Anchor Evaluation will be forthcoming upon entire completion of IE Bulletin 79-02.
See response to Item 7 of enclosure for a tentative completion schedule.
~~,~
Roger W Huston Senior Nuclear Licensing Engineer CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement Attachment (11 pages) 8001 110 1s7 9
-. **-*----** -*-~-~-~..__--**---------~**...... -------..-~-~--.
~----*-.--*------.-";"'--.. -----=---~-..,.--~---. ~--*------ ---**-:--,-.-- :----.***...
I.
GENERAL Response to PIPE SUPPORT BASE PLATE NRC ~letin 79-02, Rev 2 December 11, 1979 AND.EXPANSION ANCHOR EVALUATION FOR PALISADES NUCLEAR PLANT CONSUMERS POWER COMPANY US NRC IE Bulletin 79-02, Rev 2, dated November 8, 1979 requested certain information within 30 days of the issuance date of the bulletin.
The following is a response to Items S, 6, 7 and 8 of the bulletin.
Item 5 Determine the extent that expansion anchor bolts were used in concrete R2 block (masonry) walls to attach piping supports in Seismic Category 1 R2 systems (or safety-related systems as defined by Rev 1 of IE Bul-
- R2 letin 79-02).
If expansion anchor bolts were used in concrete block R2 walls:
R2
- a.
Provide a list of the systems involved with the number of supports, R2 type of anchor bolt, line size and whether these supports are ac-R2 cessible during normal plant operation.
R2
- b.
Describe in detail any design consideration used to account for R2 this type of installation.
R2
- c.
Provide a detailed evaluation of the capability of the supports, R2 including the anchor bolts and block wall to meet the design loads.
R2 The evaluation must describe how the allowable loads on anchor R2 bolts in concrete block walls were determined and also what analyt-R2 ical method was used to determine the integrity of the block R2 walls under the imposed loads.
Also describe the acceptance cri-R2 teria, including the numerical values, used to perform this eval-R2 uation.
Review the deficiencies identified in the Information R2 Notice on the pipe supports and walls at Trojan to determine if a R2 similar situation exists at your facility with regard to supports R2 using anchor bolts in concrete block walls.
R2
- d.
Describe the *results of testing of anchor bolts in concrete block R2 walls and your plans and schedule for any further action.
R2 Response to Item 5
- a.
As a result of actual verification performed at Palisades, a total of five safety seismic system pipe supports/restraints have been identified which were installed on concrete block walls.
The systems 1
Response to NRC
~letin 79-02, Rev 2 December 11, 1979 involved, number of supports, line size and accessibility are as shown in Table 1.
The location and size of these block walls are shown in attached Figures I and II.
- b.
The specific original design criteria for these particular hanger/block wall combinations have not been found (see Item c).
- c.
An evaluation of block walls supporting the safety seismic supports, as identified above, has been made to determine the ability of these block walls to resist seismic effects under operating basis earthquake and safe shutdown earthquake conditions, including known pipe support loads.
- All such walls satisfy the acceptance criteria with the exception of a blockout filled with masonry blocks within the reinforced concrete wall separating the diesel generators.
This blockout within the concrete wall and the hanger supports will be modified as appropriate to meet the acceptance criteria.
None of these block walls are intended to act as shear walls.
The method of analysis, loading combinations and the acceptance criteria are described in Section VI.
- d.
The testing of these particular expansion anchor bolts in concrete block walls has not been performed to date.
The expansion anchor bolts installed in concrete block walls will be either tested or replaced by through-bolts, or hanger supports will be relocated as appropriate for safety-related seismic piping.
2
Response to NRC TABLE 1-79-02 Rev 2 Pipe Support/
Pipe l1etin 79-02, Rev 2 December 11, 1979 Anchor Accessible Bolt During Plant System Pipeline Restraint Elevation Area/Room Type Operation eves HC-16-3" Hl0.1 592'-3-5/8" 2/Charging EA Yes Pumps eves HC-16-3" Hll.1 595'-3-5/8" 2/Charging EA Yes Pumps Containment GC-3-8" R125.1 (Riser) 2/E Safeguard TB Yes Spray Service Water HB-23-6" H-60 599'-8" 4/Diesel TB Yes Generator eves
- HCC-100-3" Hl.3 Riser 2/Charging EA Yes
- This piping is to be removed in early 1980 as part of installation of charging pump suction stabilizers.
- Expansion Anchor TB
- Through-Bolt CVCS - Chemical Volume and Control System Item 6 Determine the extent that pipe supports with expansion anchor bolts used
- R2 structural steel shapes instead of base plates.
The systems and lines R2 reviewed must be consistent with the criteria of IE Bulletin 79-02, R2 Rev 1.
If expansion anchor bolts were used as described above, verify R2 that the anchor bolt and structural steel shapes in these supports R2 were included in the actions performed for the.Bulletin. If these R2 supports cannot be verified to have been included in the Bulletin R2 actions:
- a.
Provide a list of the systems involved, with the number of supports, R2 type of anchor bolt, line size and whether the supports are acces-R2 sible during normal plant operation.
R2
- b.
Provide a detailed evaluation of the adequacy of the anchor bolt R2 design and installation.
The evaluation should address the assumed R2 distribution of loads on the anchor bolts.
The evaluation can be R2 based on the results of previous anchor bolt testing and/or analy~is R2 which substantiates operability of the affected system.
R2 3
Response to NRC ~etin 79-02, Rev 2 December 11, 1979
- c.
Describe your plans and schedule for any further action necessary R2 to assure the affected systems meet Technical Specifications opera-R2 bility requirements in the event of an SSE.
R2 Response to Item 6
- a.
A list of safety seismic system pipe supports using expansion anchor bolts and structural steel shapes instead of base plates is given in Table 3.
This list has been developed from the available information collected at the Palisades Plant as a result of actual "walkdown" of safety seismic systems.
As the piping walkdowns are completed, additional supports similar to those in Table 3 will be identified.
- b.
The evaluation of pipe supports using structural shapes instead of base plates shall be on a case-by-case basis.
In general, this evaluation will be similar to the analyses currently being performed for base plates.
Item 7 For those licensees that have had no extended outages to perform the R2 testing of the inaccessible anchor bolts, the testing of anchor bolts R2 in accessible areas is expected to be completed by November 15, 1979.
R2 The testing of the inaccessible anchor bolts should be completed by the R2 next extended outage.
For those licensees that have completed the
- R2 anchor bolt testing in inaccessible areas, the testing in accessible R2 areas should continue as rapidly as possible, but no longer than R2 March 1, 1980.
The analysis for the Bulletin items covering base plate R2 flexibility and factors of safety should be completed by November 15, R2 1979.
Provide a schedule that details the completion dates for R2 IE Bulletin 79-02, Rev 2, Items 1, 2 and 4.
R2 Response to Item 7 The schedule for completion of inspection and testing of safety seismic pipe supports using expansion anchors for Items 1, 2 and 4 of NRC IE Bulletin 79-02, Rev 2, is as follows:
Area Description Areas inaccessible during plant operations (ie, containment and other selected areas).
Areas accessible during plant operations.
Items deemed inaccessible, re-gardless of plant operational status because of location, radiation, etc.
4 Optimistic Date of Completion December 30, 1979 February 1980 Will be evaluated on a case-by-case basis
Response to NRC Item 8 B~letin 79-02, Rev 2 December 11, 1979 Maintain documentation of any sampling inspection of anchor bolts re-R2 quired by Item 4 on site and available for NRC inspection. All holders R2 of operating licenses for power reactor facilities are requested to R2 complete Items 5, 6 and 7 within 30 days of the date of issuance of R2 Rev 2.
Also describe any instances not previously reported, in R2 which you did not meet the revised (R2) sections of Items 2 and 4 and, R2 if necessary, your plans and schedule for resolution.
Report in writing R2 within 30 days of the date of this revision issuance, to the Director R2 of the appropriate Regional Office, completion of your review.
For ac-R2 tion not yet complete, a final report is to be submitted upon completion R2 of your action.
A copy of your report(s) should be sent to the United Rl States Nuclear Regulatory Commission, Office of Inspection and Enforce-Rl ment, Division of Reactor Operations Inspection, Washington, DC 20555.
Rl These reporting requirements do not preclude nor substitute for the Rl applicable requirements to report as set forth in the regulations Rl
~nd license.
Rl Response to Item 8 The data from the testing program is available on site.
The analytical data is available at Bechtel, Ann Arbor.
II. CONCRETE BLOCK ANALYSIS APPROACH
- a.
Method of Analysis
- 1.
Compute the natural frequency of the wall by use of a beam or plate model.
Cracked sections are considered in the calculation.
- 2.
Refer to the appropriate floor response.spectra from the existing seismic analysis and calculate the peak spectral response.
The inertia load of the wall is obtained.
- 3.
Compute the maximum responses using t.he critical loading combination stated in Section b and compare with the acceptance criteria provided in Section c.
This includes local and global wall bending and local and global wall shears.
- 4.
For pipe supports for which loads are not known at this time, a preliminary evaluation has determined that reserve strength is available beyond that required for inertial load.
- b.
Loading Combination The loading combinations used in the investigation are the following:
- 1.
(D + L + E)
- 2.
(D + L + R + E')
5
---. ---;--.~-...-~*-::--*-**---:---*....-~--~~-----------.-.-~-------*-------:--*-"7*-.;---;---.-..*-**-*--*-**;..---**-... -;"-*..,-***-.. : ***-* **--.--... --......... -
Response to NRC lletin 79-02, Rev 2 December 11, 1979
- 3.
(D + L + H + E')
where D = dead load L = live load R = pipe rupture load H = pipe operating thermal load E
= design seismic load for Class 1 structures E' = maximum ~eismic load for Class 1 structures
- c. Acceptance Criteria Acceptance criteria for the load combination given above are as follows:
- 1.
Loads involving E:
use Uniform Building Code (denoted as S) (See Item C.3 for allowable stresses, 'S'.)
- 2.
Loads involving E':
use 1.5 times Uniform Building Code (denoted as l.5S) (See Item C.3 for allowable stresses,
's'.)
- 3.
Allowable stresses ('S') for concrete block wall with f'm = 2,000 psi on the blocks and Type N mortar are included below in Table 2.
Masonry Material
- Solid concrete masonry Grade A Grade B
- Grouted masonry TABLE 2 TYPE N MORTAR Compression (psi) 140 100 667 Shear or Tension in Flexure (psi)
Special Inspection 12 12 49 No Special Inspection 6
6
- Values obtained from UBC Table 24B, 1979 edition
- Values obtained from Supplement 1 of Bechtel response to PG&E's Trojan Plant LER-79-15 dated November 4, 1979 6
-.,.. ~,........,..--,.---,...,,..-*___.--.~---.---...,..-----~*r-.------------..-----.------------***-----***-****"**.---.-.-~...,---------.--v**.,.* *-.::'".., * ~.- * * -- *.,. *"
- r.
Stress Field Problem Isometric 03312 HBD-8-4 03312 HBD-8-1 03312 HBD-8-1 03318 M-101-65 03319 M-107-1 03319 M-107-3 03319 M-107-1 03320 M-107-16 03320 M-107-14 03322 M-107-23 TABLE 3 NRC BULLETIN IE 79-02, REV 2 LIST OF PIPE SUPPORTS WITH EXPANSION ANCHORS USING STRUCTURAL STEEL SHAPES, UNISTRUTS, OR ANCHORS AS SUPPORT System Identification Component cooling water Component cooling water Component cooling water Line Identi-fication and Size HBD-8-14" HBD-8-10" HBD-8-10" Fire system KB-1-12" Engineering safe-HC-3-24" guard pump suction Low-pressure HC-3-6" safety injection pump discharge Engineering safe-HC-3-18" guard pump suction Containment spray GC-3-8" Safety injection GC-1-12" Safety injection DC-2-4" Hanger H-4 H-7.2
- .; H-10 H-6.4, H-151.3 H-166.3 H-212 R-121.1 R-143.1 H-4 Type of Expansion Anchors Wedge Shell Wedge Shell Shell Shell Wedge Shell Wedge Shell Accessible During Normal Plant
.operation Remarks Angle attachment Angle attachment Angle attachment Angle attachment Threaded hanger rod in anchor shell Plate bolted to unistrut Channel and plate ~
attachment Channel attachment Channel attachment Threaded hanger rod in anchor shell l
NRC IE Bulletin 79-02, Rev 2 Table 3 r
Accessible During Line Identi-Type of Normal Stress Field System fication Expansion Plant P.roblem Isometric Identification and Size Hanger Anchors Operation Remarks 03324 M-107-98 Spent fuel cooling HC-4-8" H-226.1 Shell Angle attachment 03324 M-107-98 Spent fuel cooling HC-4-8" H-228.1 Angle attachment 03324 M-107-33 Spent fuel cooling HC-4-6" H-229.2 Unistrut attachment 03324 M-107-28 Spent fuel cooling HC-4-6" R-235.1 Shell Channel attachment 03329 HCC-45-2 Radwaste acid HCC-45-3"
- H-16 Shell Channel attachment-process 03329 HCC-45-2 Radwaste acid HCC-45-3" H-17 Shell Channel attachment process 03329 M-107-117 Radwaste acid HC-2-3" H-168.1 Shell Threaded hanger process rod in anchor 03353 M-101-194 Service water JB.-16-6" H-2 Shell Threaded hanger cooling rod in anchor 03355 FSK-JB-16-1 Piping for air JB-16-12" H-1 NA Plate bolted to space purge fan embedded unistrut 03355 FSK-JB-16-1 Piping for air JB-16-12" H-2 Shell Threaded rod in space purge fan anchor e
03355 FSK-JB-16-1 Piping for air JB-16-12" H-3 Shell Threaded rod in space purge fan anchor 03355 FSK-JB-16-1 Piping for air JB-16-12" H-4 Shell Threaded rod in space purge fan anchor NRC IE Bulletin 79-02, Rev 2 Table 3 Accessible During Line Identi-Type of Normal Stress Field System fication Expansion Plant Problem Isometric Identification and Size Hanger Anchors Operation 03356 M-101-14 Auxiliary feed HB-35-6" H-932 Shell pump 03362 M-107-54 Safety injection CC-4-12" H-739 Shell 03366 M-107-65 High-pressure DC-1-6" H-707 7 - Shell safety injection 1 - Wedge to primary loop 03368 M-107-64 Redundant high-CC-6-6" H-714 Shell pressure safety injection 03372 FSK-EB-9-2 Feedwater to Steam EB-9-18" H-30 Shell Generator B 03372 FSK-EB-9-2 Feedwater to Steam EB-9-18" H-31 Shell Generator B 03378 M-107-22 High-pressure DC-1-6" H-209 Shell sAfety injection An additional list of similar supports will be provided as information becomes available as a result of field surveys at the conclusion of the present scope of work for IE Bulletin 79-02. Remarks Anchors through embedded channel Angle attachment Angle attachment Anchors through embed plate Anchors through.
embed plate Angle attachment r*
e
I **
- i j.,
' l
- 1 :
1 i
© D
c l2 A
6 5
4 z
MDUltHl.
Ml MOH tau ~*1l4T /1~ GAL....
tfo PIH ln1w~1a11ea c.9i PIH **,".... Yl*Mt:* Dl't c*e*
0 tfl*.,._. WtO **T1wQ4tlU*&
-¢'
,ALL ~*~* Ot'f llCNTll COMPANY
- AllSAOU PLANT CONSUMUS rowu C0-.4PAN fQUIDllf~T LCC4.T1:'o,,i
-1?~.i\\C~:'
PLAN.,. EL S7c*-
- ,;;nc
. ~.,
5935 !
M - I
-- r I I I I I I tr;! I I
H
(~ - ---~~*.
G D
c I
A 7 -
s 2