ML20117M511
| ML20117M511 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek, Susquehanna, 05000000 |
| Issue date: | 05/13/1983 |
| From: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Allan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20114G054 | List:
|
| References | |
| FOIA-84-616 NUDOCS 8505170113 | |
| Download: ML20117M511 (2) | |
Text
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MAY 131983 MEMORANDUM FOR:
J. M. Allan, Acting Regional Administrator FROM:
R. W. Starostecki, Director, DPRP
SUBJECT:
CY 83 SALP SCHED'JLE, REVISION 2
-SALP schedules were previously pmvided by memorandums of November 26, 1982 and Revision on January 17, 1983.
Some changes have been made for the latter part of 1983.
The attached schedule is marked to show the dates that are revised.
All persons who contribute to the SALP. report for a specific licensee are requested to provide input to the DPRP Section Chief, through their Branch management, 25 calendar days before the scheduled SALP Board date.
The material 'provided to Section Chiefs should be written in the SALP format.
The Oyster Creek Report dated April 19,.1983 and the Susquehanna report are representati' e of the quality desired.
dated April 26, 1983 v
By separate memo, Office Directors and Regional Administrators are provided a copy of this ' schedule.
^
Richard W. Starostecki, Director Division of Project a'nd Resident Programs
. Enclo sure :
As stated cc w/ enclosure:
T. T. Martin Technical Assistants Branch Chiefs Section Chiefs Resident Inspectors PA0-g40@"
$ 0
,616
e-n u wa &
- ) w CY 83 SALP PROGRAM SCHEDULE Mana gemi Input Due to Board Meeti ng Facili ty Assessment Period Section Chief Meeting (Week o' Peach Bottom 2&3 3/1/82 - 2/28/83 3/17/83 5/16/83 6/6/83 jYankee 5/1/82 - 4/30/83 5/5/83 5/31/83 6/27/83
- NMP-1 5/1/82 - 4/30/83 5/12/83
~6/6/83 6/20/83
- Vermont Yankee 5/1/82 - 4/30/83 5/19/83 6/13/83 6/27/83 Ginna 6/I/82 - 5/31/83 6/9/83 7/5/83 7/18/83 lMaina Yankee 7/1/82 - 6/30/83 7/7/83 8/1/83 8/2?/83 Seabroo k 7/N82-6/30/83 7/14/83 8/8/83 A /?? /93
' Pi l grim 7/1/82 - 6/30/83 7/28/83 8/22/83 9/6/83 Hope Creek 1 8/1/82 - 7/31 /82 8/4/83 8/29/83 9/13/83
, Millstone 3 9/1/82 - 8/31/83 9/22/83 10/17/83 11/14/8:
Millstone 1&2 9/1 /82 - 8/31 /83 9/29/83 10/24/83 11/14/S:
Haddam Neck 9/1/82 - 8/31/83 10/6/83 10/31/83 11/14/8:
Salem 1 &2 10/1/82 - 9/30/83 10/13/83 11 /7/83 11/21/8:
TMI-2 10/1/82 - 9/30/83 10/20/83 11/14/83 12/12/S:
NMP-2 10/1/82 - 9/30/83 10/?7/83 11 /21 /83 12 /5 /??
TMI-1 10/1/82 - 9/30/83 11/3/83 11/28/83 12/12/8:
Calvert Cli'ffs 1&2 10/1/82 - 9/30/83 11/10/83 12/5/83 12/19/8; Limerick 1 &2 12/1/82 - 11/30/83 12/15/83 1/16/84 1/20/84
- Revised schedule is underlined.
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ypy 17 933 Docket No. 50-255 J
Consumers Power Company ATTN:
Mr. D. J. VandeWalle j
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Nuclear Licensing Administrator I
N 212 West Michigan Avenue Jackson, Michigan 49201 W#
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Gentlemen:
Thank you for your letter dated April 28, 1983, providing updated infor-rtation relative to Licensee Event Report 83-06, including your proposed schedule for modifications to the Safety Injection Refueling Water (SIRW) tank support structure to bring the support structure into accordance with the FSAR and ACI Code.
In response to LER 83-06 dated February 17, 1983 a member of the NRC Region III staff and the NRC Resident Inspector conducted an independent inspection of the SIRW tank support structure (Reference Inspection Report No. 50-255/83-08). Additionally, the NRC Region III staff member met with personnel from Consumers Power Company and Bechtel to review their analysis of the support structure.
Based upon the updated information, the results of the inspection, review of your analysis of the existing support structure, your conrnitment to conduct quarterly inspections until the structure is modified, and consid-ering the extent and number of activities already scheduled for the 1983 outage, Region III concurs with your plan to do the remedial work during the 1985 refueling outage..
We request that Consumers Power Company apprise Region III of the results of the quarterly inspection through the NRC Resident Inspector. It is also requested that the Region III staff participate in the initial quar-terly inspection and a minimum of one additional inspection. Also, that the NRC Resident Inspector participate in any or all of the anticipated inspections.
S M 'Ma m
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l Consumers Power company MAY 171953 The Region III staff will be in contact with Consumers Power Company cognisant personnel to determine the availability for review of the necessary procedures, work packages, and method of repair for the mod-ifications to the SIRW tank support structure.
We will gladly discuss any questions you may have regarding this matter.
l Sincerely, 1
l l
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.R. L. Spessard, Director Division of Engineering ces R. W. Montross, Manager cc w/ltr dtd 4/28/83:
DMB/Docu: Lent Control Desk (RIDS)
Resident Inspector, R III Ronald Callen, Michigan Public Service Comission
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Consumcis Power Company Generet offices 212 West MacNeen Avenue Jockeon, Ms 49201 + (617) 788-0550 April 28, 1983 James G Keppler, Administrator Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn. IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LICENSEE EVENT REPORT 83-06 (SIRW TANK SUPPORT STUCTURE DISCREPANCIES) UPDATE Consumers Power Company reported a discrepancy between the actual configura-tion and the as-built design documents for the Safety Injection Refueling Water (SIRW) tank support structure in licensee event report 83-06 dated February 17, 1983. Specifically, thirteen three-foot square openings and one 26 inch by 38 inch opening are present in the concrete beams as compared to the nine openings identified on the as-built documentation. Our evaluation has concluded that although the existing condition is not in accordance with the FSAR and ACI Code, sufficient capacity to resist specified loadings is maintained. Consumers Power Company also committed to provide specific information relative to the design and schedule for proposed modifications to bring the support structure into compliance with'the Palisades Plant FSAR and ACI Code. The purpose of this letter is to provide Consumers Power Company's schedule for modifications. Design details will be available for inspection about June, 1983.
Please identify your documentation needs so that a design review package can be prepared and forwarded to you when it becomes available.
The currently selected optimum design fix would involve relieving the stress l
in the SIRW tank support beams by draining most of the water from the SIRW l
tank and filling the eight openings in the north-south beams of the support structure with concrete and steel reinforcement bars to provide adequate shear capacity in the SIRW tank support beams. Steel reinforcing bars would be doweled into the beam webs to transfer the shear force from the existing web to the repair. Conduit and piping presently routed through the foundation would be rerouted for accessibility. Engineering design efforts are presently ongoing and currently scheduled to be complete about June 1983. Subsequent efforts include: review of the design by Consumers Power Company, the develop-ment of construction work packages, the performance of pre-outage work such as the procurement of materials, the fabrication and installation of piping and supports on the building roof, preparation of electrical conduit and viring for dismantling and rearranging and the commencement of core drilling in SIRW tank support beams to accommodate the aforementioned dowel pins. These preparatory activities are estimated to take about 12 weeks to complete. Actual OC0483-0012A-NLO2 MAY 21983
% merm w
4 JGKeppler, Administrator 2
Palisades Plant LER 83-06 UPDATE i
'1 April 28 -1983
' outage work is estimated to take 10'veeks to complete with concrete curing controlling much of the critical path because the SIRW tank must be empty during.that time.
Currently we have accelerated.the start date of the 1983 Palisades refueling oustage from October 15, 1983.to August 13, 1983.
This is due to the excellent plant availability that Palisades has demonstrated in the past eight months (> 97%) and our extensive outage planning effort which has scheduled
.all outage work for the contigency of an early start by as much as 60 to 90 days.
This refueling outage includes several projects and programs critical to the continued safe operation of Palisades such as the 10-year Inservice Inspection including the mechanized reactor vessel exams and core barrel removal and associated exams, installation of a third auxiliary feedwater. pump, completion of the control room habitability modifications and upgrades, remedying the leaking safety injection bottle check valves, completing the Systematic Evaluation Program modifications as previously committed in the Integrated Assessment, and performing other significant activities including the sipping of a majority of the nuclear fuel, steam generator inspections, major turbine inspections and main electrical generator availability improvement modifica-tions. Although complete manpower loadings for all work are not now available, it is estimated that there will be 1100 to 1400 personnel working on site during peak periods of the outage.
To allow for more detailed planning of the actual. implementation of the proposed SIRW tank support structure design, to provide sufficient lead time for all materials, and to accommodate evaluating alternative engineering fixes, the merits of planning this fix for the 1985 Palisades refueling outage are extremely attractive.
-In light of these considerations and based upon our detailed analyses which indicate that the existing structure does not adversely affect the health and safety of the public, Consumers Power. Company is proceeding with planning the SIRW tank structural design fix as an integral part of the 1985 refueling outage. In the interim, Consumers Power Company intends to conduct quarterly inspections of the structure by a team of structural engineers. The purpose of this inspection will be to identify significant changes in structure that may have a potential for adversely af fecting structural adequacy.
20(
David JWandeWalle Nuclear Licensing Administrator CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NkC Resident Inspector - Palisades OC0483-0012A-NLO2 a
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Consumers Power Company ATTN: Mr. D. J. VandeWalle Nuclear Licensing Administrator 212 West Michigan Avenue
' Jackson, Michigan 49201 Gentlemen:
Thank you for your letter dated April 28, 1983, providing updated infor-mation relative to Licensee Event Report 83-06, including your proposed schedule for modifications to the Safety Injection Refueling Water (SIRW) tank support structure to bring the support structure into accordance with the FSAR and ACI Code.
In response to LER 83-06 dated February 17, 1983 a member of the NRC Region III staff and the NRC Resident Inspector conducted an independent inspection of the SIRW tank support structure (Reference Inspection Report No. 50-255/83-08). Additionally, the NRC Region III staff member met with personnel from Consumers Power Company and Bechtel to review their analysis f
of the support structure.
Based upon the updated information, the results of the inspection, review of your analysis of the existing support structure, your com=itment to conduct quarterly inspections until the structure is modified, and consid-l ering the extent and number of activities already scheduled for the 1983 outage, Region III concurs with your plan to do the remedial work during the 1985 refueling outage.
We request that Consumers Power Company apprise Region III of the results
-of the quarterly inspection through the NRC Resident Inspector.
It is also requested that the Region III staff participate in the initial quar-terly inspection and a minimum of one additional inspection. Also, that the NRC Resident Inspector participate in any or all of the anticipated inspections.
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Consumers Fover Company ray 17 id3 The Region III staff will be in contact with Consumers Power Company cognisant personnel to determine the availability for review of the necessary procedures, work packages, and method of repair for the mod-ifications to the SIRW tank support structure.
We will gladly discuss any questions you may have regarding this matter.
Sincerely, A_y
.R. L. Spessard, Director Division of Engineering cc:
R. W. Montross, Manager cc w/Itr dtd 4/28/83:
DMB/ Document Control Desk (RIDS)
Resident Inspector, R III Ronald Callen, Michigan Public Service Comission l
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U April 28. 1983 James C Esppler. Administrator Region III US Nuclear Regulatory Commission 799 acomevelt Road Glen Ellyn. IL 60337 t
DOCKET S0-255 - LICENSE DPR FAL15ADES PLANT - LICENSEE EVENT REPORT 83-06 ($1RW TAXK SUpp0RT STUCTURE DISCREFANCIES) UPDATE Consumers Feuer Company reported a discrepancy between the actual configura-tion and the as-built design documents for the Safety Injection Refueling Oter (SIRW) tank support structure in licensee event report 83-06 dated T bruary 17. 1983.
Specifically, thirteen three-foot aquara openings and one 26 inch by 38 inch opening are present in the concrete beams as compared to the mine openings identified on the as-built documentation.
Our evaluation has concluded that although the existing condition is not in accordance with the FSAR and ACI Code. sufficient capacity to resist specified loadings is maintained.
Consumers Power Company also committed to provide specifie inforlastion relative to the design and schedule for proposed modifications to' bring the support structure into compliance with the Palisades Plant TSAR and ACI Code.
The purpose of this letter is to provide Consuners Power Ccs:pany's ochedule for modifications.
Design details will be available for inspection cbout June, 1983.
Pl. ease sdentify your documentation needs so that a design review package can be prepared and forwarded to you when it becomes available.
The currently selected optimum design fix would involve relieving the stress ita the SIRW tank support beams by draining most of the water from the SIRW tcak and filling the eight openings in the north-south beams of the support otructure with concrete and steel reinforcement bars to provide adequate ahear ccpacity in the SIRW tank support beans.
Steel reinforcing bars would be doweled into the beam webs to transfer the shear force from the existing web to the repair.
Conduit and piping presently routed through the foundation would be rerouted for accessibility. Engineering design efforts are presently engoing and currently scheduled to be complete about June 1983.
Subsequent afforts includes review of the design by Consumers Power Company, the develop-meat of construction work packages, the performance of pre-outage work such as the procurement of materials, the fabrication and installation of piping and cupports on the buildins roof, preparation of electrical conduit pod wiring for dismantling and rearranging and the copunencement of cora drilling in SIRW tank support beams to accosanodate the aforementioned dowel pins.
These preparatory activities are estimated to take about 12 weeks to complete. Actual OC0483-0012A-NLO2
@4p% j yi y
JCKeppler. Administrator 2
Felisades Plant LER 33-06 UFDATE April 28, 1983 outage work is estimated to take 10 weeks to complete with concrete curing controlling much of the critical path because the SIRW tank must be empty during that time.
Currently we have accelerated the start date of the 1983 Falisades refueling ovatage from October 15, 1983 to August 13, 1963.
This is due to the excellent plant availability that Falisades has demonstrated in the past eight months (* 97%) and our extensive outage planning effort which has scheduled all outage work for the contigency of an early start by as much as 60 to 90 j
days.
4 This refueling outage includes several projects and programs critical to the continued safe operation of Palisades such as the IO-year Inservice Inspection i
including the mechanized reactor vessel exams and core barrel remova3 and associated exams, installation of a third auxiliary feedwater pump, completion l
of the control room habitability modifications and upgrades, remedying the leaking safety injection bottle check valves. completing the Systematie Evaluation Program modifications as previously committed in the Integrated Assessment, and performing other significant activities including the alpping j.
of a majority of the nuclear fuel, steam generator inspections, major turbine
(:
inspections and main electrical generator availability feprovement modifica-i tions. Although cooplete manpower loadings for all work are not now
.available, it is estimated that there will be 1100 to 1400 personnel working l
en site during peak periods of the outage.
To allow for more detailed planning of the actual implementation of the proposed SIRW tank support structure design, to provide sufficient lead time for all materials, and to accommodate evaluating alternative engineering fixes, the merits of planning this fix for the 1985 Falisades refueling outage are extremely attractive.
In light of these considerations and based upon our detailed analyses which indicate that the existing structure dees not adversely offect the health end saf ety of the public. Consumers Power Company is proceeding with planning the SIRW tank structural design fix as an integral part of the 1985 refueling outage.
In the interim Consumers Power Company intends to conduct quarterly inspections of the structure by a team of structural engineers.
The purpose of this inspection will be to identify significant changes in structure that may have a potential for adversely affecting structural adequacy.
David J VandeWalje (signed)
David'J Yandekalle Nuclear Licensing Administrator CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident inspector - Fa11sades OC0483-0012A-NLO2
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FROM: R M KRICH. PALISADES CC:
R B DEVITT, P26-!! 7B. JACKSON
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D J VANDEWALLE. P24-614B. JA CK SO N THIS CONFIRMS PROMPT NOTIFICATION OF AN OCCURRENCE REPORTABLE P l
TS 6.9.2.A.(2).
ON JANUARY 29, 1983. OPERATORS DISCOVERED THAT THE THERMAL OVERLOADS FOR ONE ROOM COOLER FAN IN EACH OF THE EN3INEER SAFEGUARDS ROOMS WAS TRIPPED PREVENTING THE FANS FROM STARTING ON A l
HIGH ROOM TEMPERATURE SIGNAL.
A SECOND FAN IN ONE OF THE ES ROOMS wuimisen..
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WAS ALSO FOUND TO HAVE BEEN WIRED INCORRECTLY, JON JANUARY 31, 1983, RESULTING IN THE FAN RUNNING B ACXWARDS.
CONDITION REPORTABLE PER TS 3.5.2. F.
THE THERMAL OVERLOADS WERE RESET ON JANUARY 29, 1933 l
AND THE WIRING WAS CORRECTED ON JANUARY 31, 19835 ' REPORTABILITY DETERMINED ON FEBRUARY 9, 1983.
INITIAL REPORT TO NRC RESIDENT INSPECTOR, J HELLER, ON FEBRUARY 9, '1933.
1251 EST NNNN FEB 14 G83 w u 1201 58 M 80, I
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General offices: 312 West Michleen Avenue, Jackson, MI 49201 * (517) 788 4650 February 17. 1983 pg gg James G Keppler Administrator Region III US Nuclear Regulatory Conunission 799 Roosevelt Road Glen Ellyn. IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LICENSEE EVENT REPORT 83-07 (LESS THAN DESIGN AIRFLOW FOR ENGINEERING SAFEGUARDS ROOM AIR COOLER)
On the reverse please find Licensee Event Report 83-07 (Less Than Design Airflow For Engineering Safeguards Room Air Cooler) which is reportable to the NRC per Technical Specification 6.9.2.a(9).
J Brian D Johnson Staff Licensing Engineer CC Director. Office of Nuclear Reactor Regulation Director. Office of Inspection and Enforcement NRC Resident Inspector - Palisades l
FEB 22 "
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Commonwe:lth Edison
,5,* Ona First N'tiorul PI:m. Chic"go, ilhnois I (/
J w)- Address Reply to: Post Office Box 767 T^^>
Chicago, Illinois 60690 i
JMitj0.lFAL STAFF May 24, 1983 qpg D/r.A i te s 1 0@drl K.@[12MD 4
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ia i Mr. James G. Keppler, Regional Administrator P)-~~i ~
j Directorate of Inspection and
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Enforcement - Region III Y.L _
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U.S. Nuclear Regulatory Commission OL l
[TE)A U 799 Roosevelt Road Glen Ellyn, IL 60137 g,g
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Subject:
Dresden Station Unit 2, Main Steam Line Snubber Failure NRC Docket No. 50-237
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/ w-Reference (a):
B. Rybak letter to J. G. Keppler dated May 13, 1983.
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Dear Mr. Keppler:
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,g E mHa sect 8
As delineated in our May 13, 1983 response (Reference
)
concerning the Dresden Station Unit 2 Snubber Action Plan the following items were to be sent to you on May 20, 1983:
7 1
1)
Correlation of test data with analysis, 2)
Determine why there was a mismatch and why it was not
{
identified, 3)
Provide MSIV analysis results, y_
4)
Compare SRV test results to MSIV analyzed loads.
q 5)
Plan for performing interference checks on the MSIV 4
line snubber pipe clamps during the 62 day technical specification snubber inspection.
T l
Response to items 1) and 3) is in the form of attachments to 4
this letter which were provided by Sargent and Lundy.
As stated in their test correlation report, here is an ongoing effort to determine potential reasons for the discrepancy between expected values and actual test l
values of the line thermal movements.
It should be pointed out, however, that the growth even though different than expected do not present a safety concern.
This was addressed in detail in our May 13, 1983 C
submittal.
We will provide an update of the further investigation to
}
l resolve the thermal growth discrepancies with our May 27, 1983 submittal.
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WY 251983
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J. G.-Keppler May 24, 198T The results of the MSIV closure analysis indicate that the loads
~
generated during that event-are on the same order of magnitude. as.those
' measured during the SRV discharge event.
Considering,-then, that piping analyses are conservative and that the analyzed MSIV closure loads are on the same: order of magnitude as the measured SRV loads, _which were in themselves very low, we~still feel that the MSIV closure event is not the cause of the snubber failure.
The information which could be gained by actually performing a MSIV isolation does not. justify the challenge to the plant safety systems.
In response to item 2 the Dresden Quality Control Department performed an investigation of the type of pipe clamps that were installed with the MSIV snubbers.- As stated in our May.13 response it appears that all the pipe clamps are NPS clamps, and not the required Pacific Scientific clamps.
These clamps were purchased and installed by Phillips Getschow Co.
In a documentation review, it.was discovered that Phillips Getschow had ordered Pacific Scientific clamps from NPS Industries.
In addition, they required a " Certificate of Conformance" as Quality
. Assurance documentation.
Their receiving documents include a Certificate of Compliance to a material specification.
They had received the clamps with.the assumption that they were Pacific Scientific clamps.
We
- acquired photographs 'of the installed clamps that were _taken by NUTECH.
The pictures showed that the clamps were not Pacific Scientific.- At that time,-a telephone call ~to NPS was made to try to determine which type of clamp was shipped.
NPS confirmed they had shipped NPS clamps and not the Pacific Scientific-clamps that were ordered.
Furthermore, they said it was a-common practice of theirs to make this type of substitution.
L In our opinion, there were.three problems with the purchasing and receiving of these clamps.
First, NPS should not have made a substi-tution without informing Phillips Getschow.
Second, Phillips Getschow's
- purchase order should have required a Certificate of Conformance to a Pacific Scientific part. number.
Third, while receiving _the clamps it j
should have been noted that the Certificate of Compliance did not certify l
that the clamps were Pacific Scientific.
It only certified the material l
type of~the clamps.
Again, as stated in our May 13 response this does not present an l
immediate safety concern.
Non-conformance~ reports, however, are being written by both the. contractor and our Station Construction Departments to address corrective for the specific problem and to prevent recurrence.
Finally, we committed:to have a plan for checking for clamp interference during the Dresden Unit 2 62 day snubber inspection.
We would like to defer this submittal until June 3 to enable us to review the results of the ' binding study which is due May 27 and incorporate the binding study will provide valuable information for defining the specific areas for inspection depending on the of binding postulated.
J..G.
Keppler
~3 -
May 24, 1983 If.there are any questions on the above, please contact this o f fice. - Per the action plan the next transmittal will be May 27, 1983.
Very truly yours, B. Ryba Nuclear Licensing Administrator 1m-c c :- NRC Senior Resident Inspector - Dresden w/o Att.
R. Gilbert - NRR w/Att.
Attachments 6639N
i SARGENTQ LUNDY E N GIN EE RO CHICASO ATTACHMENT A A. forced vibration time history analysis was performed to determine the effects on the main steam header C and the associated SRV piping resulting from dynamic loads acting on the main steam piping due to Main Steam Isolation valve (MSIV) closure.
Based on the information contained in the FSAR, the steam flow rate through the valve was taken as 6
2.45 x 10 lb/hr.at a pressure of 9'65 psia.
The valve.
closure from 100% to 0% flow was taken as a linear function of time and the closure time was taken as 1.8 sec (provided by Commonwealth' Edison Company).
The force time history.was generated using in-house computer program 'HYTRAN'.
The resulting piping supp' ort loads caused by the MSIV closure event are given in the attached table.
From the table, it is seen that the MSIV closure loads are bounded.by.the
.+
SRV discharge loads.
It should be noted that the SRV discharge loads given in the attached table'were obtained with a relatively slow valve opening time of 280 msec.
With a faster opening time of-60 msec for the SRV, the MSIV closure loads will become insignificant relative to the SRV transient loads.
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SARGENT & LUNDY EN GIN E E R0 CHICAGO TABLE COMPARISON BETWEEN SRV DISCHARGE AND MSIV CLOSURE LOADS (MS-C SUBSYSTEM)
Snubber ID SRV Discharge Load MSIV Closure Load (Valve Opening Time = 280 nSec)
Closing Time = 1.8 Sec l
- 50 (1bs)
$ 2-3001C-S1 (abs)
(M-564G-1) 1560 785 NP 27 (X-Skew)
- 51 2-3001C-S2 1822 i
(M-564G-2) 1514 NP 28 (X-Skew)
- 44 2-3001C-S3 (M-564G-3) 1617 719 NP 55B (X-Glob)
- 54 2-3019C-S2 1141 149 (M-564G-9) i l
NP 119 (X-Skew) 055 l
2-3019C-S1 632 83 l
(M-564G-8)
NP 120 (Z-Skew) l I
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