RBG-32247, Application for Amend to License NPF-47,revising Div I & II Diesel Generator Crankshaft Insp Scheduling Contained in Attachment 3 to License & Surveillance Requirement 4.8.1.1. Change Requested Prior to Third Refueling Outage
| ML20006E022 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 02/02/1990 |
| From: | Deddens J GULF STATES UTILITIES CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20006E023 | List: |
| References | |
| RBG-32247, NUDOCS 9002160090 | |
| Download: ML20006E022 (8) | |
Text
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y GULF STATES UTILITIES COMPANY RNi R St 40 (T A'Oh PD$fOsplCIt@ )M
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February 2,1990 RBG-32247 i
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U.S. Nuclear Regulatory Commission.
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Document Control Desk.
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- Gentlemen
River Bend Station.-: Unit 1
,C, Docket No.-50-458
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Gulf States. Utilities (GSU)Companyherebyfilesanapplication l
to amend the River. Bend Station Unit <
1 Technit.a1 l
Specifications, Appendix A to' Facility Operating License NPF-47, pursuant to 10CFR50.90. 'This application is filed to revise the d,
. Division: -I and1 II Diesel Generator crankshaft inspection 4
'iY l scheduling contained in Attachment?3.to NPF-47 and surveillance Y~
requirement 14.8.1.1.
This. proposed change is requested prior to i
b7 the third refueling outage at River Bend Station. The Attachment W
J to this' letter and Enclosure provide the justifications and
- proposed revisions t'o the Technical Specifications.
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'6 Your prompt attention to this application is appreciated. '
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, Sincerely, g
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4 J. C. Deddens aSenior Vice President q
River' Bend Nuclear Group JCD/TFP/h 10/
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Attachment n.
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U.S. Nuclear Regulatory Commission oon
'611 Ryan Plaza Drive, Suite 1000
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Arlington, TX 76011 j
NRC Resident Inspector
$d P,0. Box 1051 p0f 88 St. Franctsville LA 70775 Aq s
Walt Paulson L
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'88 U.S.: Nuclear Regulatory Commission I
MA 11555 Rockviile Pike
.Rockville, MD 20852 t
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION STATE OF LOUISIANA
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PARISH OF WEST FELICIANA
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Docket No. 50-458 In the Matter of
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GULF STATES UTILITIES COMPANY
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(River Bend Station - Unit 1)
AFFIDAVIT J.
C.
- Deddens, being duly
- sworn, states that he is a Senior Vice President of Gulf States Utilities Company; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the documents attached hereto; and that all such documents are true and correct to the best of his knowledge, information and belief.
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J. C. Deadens
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Subscribed and sworn to before me, a Notary Public in and Y[ T
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for the State and Parish above named, this @ I"b-day of
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19 M,
My Commission expires with Life, d
0Lwak J hinat Claudia P.
Hurst
- 1 Notary Public in and for West Feliciana Parish, Louisiana
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I ATTACHMENT l
i-GULF STATES UTILITIES COMPANY-RIVrli DEND STATION DOCKET 50-458/ LICENSE NO. NPF-47 i
DIESEL GENERATOR URAk'KSHAFT INSPECTION CHANGE (90-01)
LICENSING DOCUMENT INVOLVED:
LICENSE NPF-47 Condition 2.c(8)
ITEM: Number 2 PAGE:
1 Reason For Request:
In accordance w!th 10CFR50.90, a change is being requested to delete the inspection of Division II diesel generator's crankshaft that is currently required by License Condition 2.c(8), Attachment 3 to NPF-47 during the third refueling outage (RF-3).
1 As a result of experience gained during previous successful inspections and overlapping requirements of the maintenance program required by Technical Specification 4.8.1.1.2.f.1 regarding crankshaft inspections, River-Bend Station (RBS) is proposing the elimination of the redundant inspections of IEGS*EG1B scheduled for the third refueling outage. The proposed change will' result in an acceleration of the recurring 5 year inspection program while eliminating an unneccessary inspection during the refueling outage-number three (RF-3).
DESCRIPTION:
In Reference 1 the NRC accepted the design of the RBS Emergency Power-Source for Divisions I and !!.
This acceptance was based on a design maximum load of 3130 kW.
This loading produces stress levels-in the i.
crankshaft that have safety factors of 1.2 to 1.39.
The inspection program was implemented on certain components to provide further assurance of adequate service - as identified in Amendments 5 and 15 to NPF-47. The Division I (IEGS*EGIA). and II (IEGS*EG1B) diesel generators are i
Transamerica-Delaval Model DSR-48 diesel engines.with NEI Peebles generators.
They are identical units in that they have the same output l
rating. overall physical configuration, similar operating characteristics, and similar testing requirements.
Thc crankshafts in each engine are identical because they have the saa. tesign, method of fabrication, and materials of construction. Periodic testing of each diesel generator is performed at a diesel generator output level that exceeds the power requirements for'each bus in an emergency.
RBS License NPF-47 Attachment 3 currently requires inspections of the crankshaft on IEGS*EGIA and B during the second and third refueling l
outages. The inspection of the crankshaft by the revised License Condition L
required during RF-3 will include a fluorescent liquid penetrant examination of the crankpin fillets and oil holes for cylinder numbers 5,
6.. and 7, and an examination of the oil holes in the main bearing journals l
between each of these cylinders.
Page 1 of 5
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After the third refueling outage, crankshaft inspections are required every 5 years by Attachment 3 and the maintenance program required by Technical Specification 4.8.1.1.2.f.1.
The maintenance program identified in Technical Specification 4.8.1.1.2.f.1 requires that a 25% overhaul inspection be performed approximately 5 years after the engines are placed i-in service._
One engine is inspected at the refueling outage closest to 5 years and the other engine is inspected at the next refueling outage.
The 25% overhaul on IEGS*EGIA and IEGS*EG1B will be performed at RF-3 and RF-4 respectively. This inspection program requires the removal of cylinder heads, pistons, connecting rods, and the connecting rod and main bearings.
e GSU plans to perform this inspection on cylinder numbers 5 and 6 during each of these outages.
NRC reviews documented in Reference 1 (Section 5.3.4.3.2) indicates that 10E7 stress cycles of the crankshaft is the endurance limit for an infinite fatigue life without cracking of the crankshaft. One crankshaft stress cycle occurs af ter each cylinder has fired once. This requires two engine revolutions to obtain one crankshaft stress cycle.
10E7 crankshaft stress cycles are achieved after 750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br /> of diesel generator operation.
Table 1 documents the crankshaft inspection history at River Bend.
Of particular interest is the fact that the June, 1985 inspection for 1EGS*EG1A found no indications of cracking in the crankshaft.
This inspection was witnessed by the NRC's consultant, Pacific Northwest Laboratory (PNL). As a result of this inspection, reinspection of the crankshaft in IEGS*EGIA was not required until the second refueling outage 45 months later.
Table 1 also provides a listing of the crankshaft inspections performed to date on IEGS*EG18.
No indications of cracks in the crankshaft were detected during these inspections. As stated in Reference 1 the last inspection of the crankshaft for 1EGS*EG1B prior to River Bend receiving i
it's operating license was performed _ in December, 1984.
The_
next inspection of the crankshaft was performed 34 months later in October, 1987(RF-1).
Eighteen months later, the RF-2 crankshaft inspection was performed in April, 1989.
At the time of the RF-2 inspection, 1EGS*EGIB had accumulated 553.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of operation with no indications of cracking found in the crankshaft.
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TABLE 1 r
INSPECTION DATES V
Inspection Date/
Outage 12/84 6/85 9/87*
3/89*
-9/90*
3/92*
DG #
(RF 1)
(RF2)
(RF 3)
(RF4)
EGIA W
X N
Y Z
N (Operatinghours)
(190)
(330)
(562)
(687) i L
EG18 W
N Y
Y Z
(Operatinghours)
(155)
(277.5)
(497)
(553)
- - Start date for each Refueling Outage during which E
crankshaft inspections are performed W - Inspection per Reference 1. Sett10n 5.3.4.1 X - Inspection per Reference 1. Section 5.3.5.2 Y - Inspection per Attachment 3 to NPF -47 Inspection i
2 - 5 year inspection per Reference 2 and Attachment 3 N - No inspection required
- - Inspection to be eliminated.
Inspection currently required by Attachment 3 h
The combined crankshaft inspection history indicates that inspections i
performed between December, 1984 and April, 1989 represent a total of 52 months of operation with no indications of cracking detected during each crankshaft inspection. The results of these inspections, combined with the crankshaft inspection results obtained during the construction of River Bend, indicate that there is sufficient inspection history available to revise Attachment 3 to eliminate the crankshaft inspection for IEGS*EG1B at the third refueling outage only.
This proposal has been reviewed by the TDI Diesel Generator Owners Group who concluded the change is justified and reasonable.
NO SIGNIFICANT HAZARDS CONSIDERATIONS:
As required by 10CFR50.92, the following is provided to the NRC staff in support of a "no significant hazards consideratiens" determination.
- 1..No significant increase in the probability or consequences of an accident previously evaluated results from this proposed change because:
The designed load limit on the TDI diesel generators of 3130 KW was imposed to restrict the stresses applied to the crankshaft during operation.
This limit was determined to provide an acceptable margin of safety during operation as identified in Reference 1.
The purpose of the crankshaft inspection program is to provide additional assurance during the time of initial operation that fatigue i
cracks are not forming in the oil holes or fillets of the most heavily loaded ' areas of the -crankshaft.
Reference 1 and Reference 2 l
recognize that changes to the inspection requirements identified in l may be requested as additional experience is gained.
The l
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p-I TABLE 1 L
INSPECTION DATES Inspection Date/
Outage 12/84 6/85 9/87*
3/89*
9/90*
3/92*
DG #
(RF1)
(RF2)
(RF3)
(RF 4)
EGIA W
X N
Y Z
N (Operating hours)
(190)
(330)
(562)
(687)
EG1B W
N Y
Y Z
(Operating hours)
(155)
(277.5)
(497)
(553) c r
- - Start date for each Refueling Outage during which I
-crankshaft inspections are performed g
3:
W - Inspection per Reference 1, Section 5.3.4.1 X - Inspection per Reference 1, Section 5.3.5.2 Y - Inspection per Attachment 3 to NPF -47 Inspection Z - 5 year inspection per Reference 2 and Attachment 3 N - No inspection required
- - Inspection to be eliminated.
Inspection currently required by Attachment 3 I
The combined crankshaft inspection history indicates that inspections performed between December,1984 and April,1989 represent a total of 52 months of operation with no indications of cracking detected during each crankshaft inspection.
The results of these inspections, combined with the crankshaft -inspection results obtained during the construction of River
. Bend, indicate that there is sufficient inspection history available to revise Attachment 3 to eliminate the crankshaft inspection for IEGS*EGIB at
- the third refueling outage only. This proposal has been reviewed by the i
TSI Diesel Generator Owners Group who concluded the change is justified and reasonable.
NO SIGNIFICANT HAZARDS CONSIDERATIONS:
As required by 10CFR50.92, the following is provided to the NRC staff in support of a "no significant hazards considerations" determination.
1.
No significant increase in the probability or consequences of an accident previously evaluated results from this proposed change because:
The designed load limit on the TDI diesel generators of 3130 KV was imposed to restrict the stresses applied to the crankshaft during operation.
This limit was determined to provide an acceptable margin of safety during operation as identified in Reference 1.
The purpose of the crankshaft inspection program is to provide
- additional assurance during the time of initial operation that fatigue cracks are not forming in the oil holes or fillets of the most heavily loaded areas of the crankshaft.
Reference 1 and Reference 2 recognize that changes to the inspection requirements identified in
' Attachment 3 may be requested as additional experience is gained. The Page 3 of 5
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o results of crankshaft inspections between December, 1984 and April, 1989 provide a history of successful crankshaft inspections.
This inspection history provides the basis for eliminating the RF-3 inspection of the crankshaft in 1EGS*EGIB and implementing the 5 year crankshaft inspection program currently required by Attachment 3 five years earlier. The maintenance program previously discussed will require a crankshaft inspection during RF-4.
Performance of this inspection is shown in Table 1. Therefore, based on the inspection history to date, eliminating the RF-3 inspection of the crankshaft in IEGS*EG1B does not increase the probability or affect the consequences of an accident previously evaluated by the NRC.
2.
This proposed change would not create the possibility of a new or different kind of accident from any previously evaluated because:
This request does not involve a physical change in any system's configuration and no new modes of operation are introduced. The proposed change allows implementation of the already reviewed and NRC approved 5 year crankshaft inspection program five years earlier than currently required.
Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
3.
This proposed change would not involve a significant reduction in the margin of safety because:
Based on the NRC's evaluation of crankshaft stresses contained in Reference 1, the crankshafts are designed to meet their intended function at a qualified load of 3130 KW, Attachment 3 to NPF-47 has additional requirements for inspection of crankshafts should an overload occur.
This change request only removes the RF-3 inspection of the crankshaft in IEGS*EG1B based on the history of successful crankshaft inspections performed to date proves that the crankshaft design is adequate and that additional inspection of the crankshaft every refueling outage is no longer required.
The crankshafts in each standby diesel generator are identical in design, material strength, and method of construction. The crankshaft in IEGS*EGIA will have more than 750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br /> of operation at the time of the RF-3 inspection and will further verify that the crankshaft design is adequate for its intended function.
The inspection will also verify that no fatigue cracks have been initiated as a result of exceeding 10E7 stress cycles on the crankshaft.
Inspecting the crankshaft in the engine with the most operating hours provides reasonable assurance that the crankshaft in IEGS*EGiB will not fail between inspections.
At the time of the RF-2 crankshaft inspection, IEGS*EG1A had 687 hours0.00795 days <br />0.191 hours <br />0.00114 weeks <br />2.614035e-4 months <br /> of operation and 1EGS*EG1B had 553 hours0.0064 days <br />0.154 hours <br />9.143518e-4 weeks <br />2.104165e-4 months <br /> of operation.
The proposed change will implement the five year L
crankshaft long term inspection program identified in Specification 4.8.1.1.2.F.1.
This crankshaft inspection frequency has been previously reviewed and approved by the NRC in Reference 2 Section 2.1.3.8.
Therefore, the proposed changes will not involve a significant reduction in the margin of safety.
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I The proposed changes do not change the system design, function, or operation as discussed in the USA:1, Reference 1, and Reference 2 and will not increase the probability or consequences of a previously evaluated accident and will not create a new or different accident.
Adequate l
assurance of crankshaft integrity is obtained by inspecting the crankshaft that has the most operating hours and verifying that it remains crack free in the highest stress area.
As a result, the ability to perform as i
described in the USAR is maintained and therefore the proposed change e
does not result in a significant reduction in the margin of, safety.
Therefore, GSU concludes that no significant hazards are involved.
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REFERENCES:
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- 1. NUliEG-0989, Safety Evaluation Report related to the Operation of
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River Bend Station SSER 3. Section 8.3 and APPENDIX M SECTION 5.3 l
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2, NUREG-1216, Safety Evaluation Report Related to the Reliability of P
Emergency Diesel Generators Manufactured by Transamerica Delaval, 4
Inc. SECTION 2.1.3.8 l
REVISED TECHNICAL SPECIFICATION:
The requested revision is provided in the Enclosure SCHEDULE FOR ATTAINING COMPLIANCE:
As indicated above, River Bend Station is currently in compliance with requirements.
Due to the elimination of a crankshaft inspection allowed by this proposed change, this proposed change is requested to be approved by August 15, 1990.
NOTIFICATION OF STATE PERSONNEL:
A copy of this amendment request has been p rovided to the State of Louisiana, Department of Environmental Quality - Nuclear Energy Division.
ENVIRONMENTAL IMPACT APPRAISAL:
Gulf States Utilities Company (GSU) has reviewed the proposed license amendment against the criteria of 10CFR51.22 for environmental considerations.
The proposed changes do not involve a significant hazards consideration, nor increase the types and amounts of effluents that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures.
Based on the foregoing, GSU concludes that the proposed change meets the criteria given in 10CFR51.22(c)(9) for a i
categorical exclusion from the requirement for an Environmental Impact Statement.
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