ML19323E351
| ML19323E351 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/21/1980 |
| From: | Richard Bright FLORIDA POWER CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19323E353 | List: |
| References | |
| 3--3-A-3, 3-0-3-A-3, NUDOCS 8005230426 | |
| Download: ML19323E351 (7) | |
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j Power C 0 R POM A ' SON May 21, 1980 File: 3-0-3-a-3 1
Mr. Darrell G. Eisenhut Acting Director Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Crystal River Unit No. 3 Docket No. 50-302 Operating License No. DPR-72 Letter dated February 25, 1980 Information Related to Turbine-Disc Cracks
Dear Mr. Eisenhut:
In response to the subject letter, Florida Power Corporation hereby sub-mits the attached report, entitled " Crystal River l' nit 3, Low Pressure Turbine-Disc Cracking, Response to NRC letter of 2/25/80".
This report contains responses to both " generic" and " site specific" questions iden-tified in Enclosure 2 of subject letter.
The Appendix 1 of this report contains material specification data that Westinghouse considers proprietary.
Therefore, in accordance with Sec-tion 2-790 of Part 2, Title 10, Code of Federal Regulations, Florida 4
Power Corporation hereby requests the NRC to withhold Appendix 1 of the report from public disclosure.
Should you require any additional information concerning this subject, please contact this office.
Very truly yours, FLORIDA POWER CORPORATION j
Ronald M. Brigh Acting Manager Nuclear Support Services PYBhewWO9D70 8005230 k N Attachment General Office 3201 Thirty-fourin street soutn. P O Box
- 42. St Petersburg. Florida 33733 813-Bc6-5151
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t STATE OF FLORIDA COUNTY OF PINELLAS R.
M.
Bright states that he is the Acting Manager, Nuclear Support Services Department of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements j
made and matters set forth therein are true and correct to the best of his knowledge, information and belief.
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/ R. pr. Bright i
1 Subscribed and sworn to be.~ ore me, a Notary Public in and for the State 1
j and County above named, this 21st day of May,1980.
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l Notary Public, State of Florida at Large, my Commission Expires: August 8, 1983 i
TSCRN63(Notary)DN-79 L
3 INDEX 1.
Introduction 2.
Response to Generic Questions 3.
Response to Site Specific Questions 4.
Appendix 1 - Westinghouse Material Specification Data -
Westinghouse Proprietary Information 5.
Appendix 2 - Turbine Trips and Overspeeds 6.
Appendix 3 - Westinghouse Inspection Report 7.
Appendix 4 - Turbine Operating Environment Lobo (ShowCause)DN65
O DOCKET 50-302 OPERATING LICENSE NO. DPR-72 CRYSTAL RIVER UNIT 3 LOW PRESSURE TURBINE - DISC CRACKING RESPONSE TO NRC LETTER OF 2/25/80
4 INTRODUCTION This report has been prepared in response to the NRC's letter, dated February 25, 1980, concerning ultrasonic inspection of Crystal River Unit 3 l
(CR-3)turbinelowpressurediscs. This report contains responses to both
" generic' and " site-specific" questions identified in the letter.
4 i
l Florida Power Corporation is a member of the utility industry Disc Integri-i ty Task Force.
As such, responses to questions contain information and l
data that has been discussed with other utilities for consistency of an-swers and, in some cases, is considered proprietary information by Westing-house Electric Corporation (Appendix 1).
Crystal River Unit 3 turbine was inspected by Westinghouse Electric Corporation for disc cracks in March 1980 and no indications were found i
(refer to Appendix 3).
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RESP 0NSE TO GENERIC QUESTIONS i
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GENERIC QUESTIONS Florida Power Corporation requested that responses to the generic questions dSked in the 2/25/80 letter be submitted to the NRC by Westinghouse Electric Corporation after review by the Turbine Disc Integrity Task Force.
This was accomplished and verified by Mr. J.
M.
Schmerling of Westinghouse. These responses are also included as part of this report.
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..r m 2 March 14,1980 Darrell G. Eisenhut, Acting Director Division of Operating Reactors
' U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Eisenhut,
Your letters of February 25,1980, to licensees with operating Westinghouse steam turbines requested certain site specific and generic information relative to turbine disc integrity. You urged in your letter that the licensees address the generic questions and coordinate the responses through an owners' group.
Licensees with nucler> power plants and Westinghouse steam turbines have formed a Turbine Dise Integrity Task Force, with Mr. Wayne Stiede'of Commonwealth Edison Company selected as Chairman. Westinghouse has been working with this Task Force to generate responses to your generic questions.
At a Task Force meeting on March 12 and 13,1980, the utilities present prepared and approved consesus responses to each of your generic questions. The Task Force further directed Westinghouse Electric Corporation to transmit these re-O sponses directly to you. The purpose of this letter is to transmit that information to you.
It is our understanding that Mr. Wayne Stiede, Chairman of the Task Force, will also confirm to you by separate letter, the Task Force's decision to have Westing-house transmit these responses direct to you. We also understand that each utilit-y, in their specific response to your letter to that utility, will discuss the extent to which they agree with these consensus responses.
If you have any questions on these, please contact me.
Sincerely, behmerl ng, Dise Integrity Progra Manager l
W. J. Ross, Operating Reactors Branch cc:
I USNRC, Washington DC 20555
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RESP 0NSE TO r
SITE SPECIFIC QUESTI0NS a
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SITE SPECIFIC GENERAL QUESTIONS -
To be completed in 20 days er prior to startup NRC QUESTIONS
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I.
QUESTION Provide the following infonnation for each LP turbine:
A.
Turbine type l
RESPONSE
CR-3 has one tandem compound four flow, three casings, condensing,1800 RPM turf ine utilizing 44 inch last row blades in each low pressure elt 1ent.
The low pressure element is designated as a Building 31ock 281.
l QUESTION B.
Number of hours of operation for each LP turbine at time of j
last turbine inspection or if not inspected, postulated to in-spection.
RESPONSE
i 16,369 hours0.00427 days <br />0.103 hours <br />6.10119e-4 weeks <br />1.404045e-4 months <br /> i
QUESTION C.
Number of turbine trips and overspeeds.
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RESPONSE
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See Appendix 2.
QUESTION D.
For each disc:
1.
Type of material including material specifications.
2.
Tensile properties data.
3.
Toughness properties data including Fracture Appearance Transition Temperature and upper energy and temperature.
4.
Keyway temperatures.
5.
Calculated keyway crack size for turbine time specified i
in "B" above.
6.
Critical crack size.
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7.
Ratio of calculated crack-to-critical crack size.
8.
Crack growth rate.
9.
Calculated bore and keyway stress at operating design overspeed.
10.
Calculated Klc data.
11.
Minimum yield strength specified for each disc.
RESPONSE
1 1
The above information is supplied in Appendix 1.
We have been notified by Westinghouse that this information is proprietary.
II.
QUESTION Provide details of the results of any completed inservice inspec-tion of LP turbine rotors, including areas examined, since issuance of an operating license. For each indication detected, provide de-tails of the location of the crack, its orientation, and size.
RESPONSE
Florida Power Corporation contracted with Westinghouse to inspect both L.P. turbine rotor discs starting March 21, 1980.
No indica-tions of cracks were found.
The Westinghouse inspection report is in Appendix 3.
III.
QUESTION Provide the nominal water chemistry conditions for each LP turbine and describe any condenser inleakages or other significant changes in secondary water chemistry to this point in its operating life.
Discuss the occurrence of cracks in any given turbine as related to history of second water chemistry in the unit.
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RESPONSE
i See Appendix 4.
I V.
QUESTION
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If your plant has not been inspected, describe your proposed sched-ule and approach to ensure that turbine cracking does not exist in your turbine.
RESPONSE
See Question II.
Crystal River-3, at this point, is on a 1-year refueling cycle.
Inspection of the turbine is on a component basis and on a 5-year interval.
It is Florida Power Corporation's schedule to reinspect
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both LP turbine rotors prior to 1985.
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Although it is not conclusive that water chemistry causes disc cracking, we maintain our water chemistry below those limits set by 2
Westinghouse (see Appendix 4).
V.
QUESTION If your plant has been inspected and plans. to return or has returned to power with cracks, provide your proposed schedule for the next turbine inspection and the-basis for this inspection schedule.
RESP 0NSE At Crystal River-3, Westir.ghouse Electric found no indications of
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Cracks.
j VI.
QUESTION Indicate whether an analysis and evaluation regarding turbine mis-siles has been performed for your plant and provided to the staff.
If such an analysis and evaluation has been performed and reported, i
please provide appropriate references to the available documenta-tion.
In the event that such studies have not been made, consider-ation should be given to scheduling such an action.
RESPONSE
I Florida Power Corporation did analyze turbine missile probabili-ties. The following references in our FSAR 're given:
1.
1.3.2.14 page 1-6 (7-11-75) 2.
1.4.40 page 1-24 3.
5.4.3.2.3 page 5-62 4.
5.4.5.3 page 5-67 (5-8-72) i 1
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