ML20195B901
| ML20195B901 | |
| Person / Time | |
|---|---|
| Site: | 05000470 |
| Issue date: | 10/26/1988 |
| From: | Vissing G Office of Nuclear Reactor Regulation |
| To: | Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| References | |
| NUDOCS 8811020247 | |
| Download: ML20195B901 (6) | |
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Octob.r 26, 1988 PNject No. 675
'o - ] lV Mr. A. E. Scherer, Director Nuclear Licensing Combuscion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500
Dear Mr. Scherc :
$UBJECT: REQUEST FOR ADDITIONAL INFORMATION CONCERNING CHAPTERS 4, 5, 6, AND 10, AHENDMENT D, CESSAR-DC, SYSTEM 80+, HATERIALS ENGINEERING BRANCH Our Materials Engineering Branch has reviewed Amendment D of Chapter 4, 5, 6 and 10 of CESSAR-DC, System 80+ transmitted by your letter dated September 30, 1988 and has identified the need for additional information. The enclosed Request for Additional Information describes the needed information.
Our schedule calls for the information to be received within 90 days from receipt of this letter.
Sincerely,
/s/
Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
As stated cc: See next page
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October 26, 1988 Project No. 675 Mr. A. E. Scherer, Director Nuclear Licensing Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500
Dear Mr. Scherer:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING CHAPTERS 4, 5, 6, AND 10, Al1ENDMENT D, CESSAR-DC, SYSTEM 80+, MATERIALS ENGINEERING BRANCH Our Materials Engineering Branch has reviewed Amendment D of Chapter 4, 5, 6 and 10 of CESSAR-DC, System 80+ transmitted by your letter dated j
September 30, 1988 and has identified the need for additional information. The enclosed Request for Additional Information describes the needed infornation.
Our schedule calls for the information to be received within 90 days from receipt of this letter.
Sincerely, Guys.Vissing,PMojectManager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects - !!!, IV, Y and Special Projects Office of Nuclear Reactor Regulation Enslosure:
As stated cc: See next page l
i Combustion Engineering, Inc.
Project No. 675 Advanced CESSAR cc: Mr. C. B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.
7910 Woodmont Avenue, Suite 1310 Bethesda, M3ryland 20814 Mr. Ernest Kennedy Manager of Licensing Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500 4
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REQUEST FOR ADDITIONAL INFORMATION COMBUSTION ENGINEERING (CE)
CESSAR - DC MATERIALS ENGINEERING BRANCH DIVISION OF ENGINEERING AND siSTEMS TECHNOLOGY 251.11 A comparison with the St ndard Review Plan indicates that the topics described below are not included in the identified CESSAR-DC sections.
4.5.1 Control Rod Drive Structural Materials Section 4.5.1 should satisfy Regulatory Guide 1.85 "Code Case Acceptability ASME Section !!! Materials".
Section 4.5.2.1 The applicant must show that the material specification in this section satisfies the requirements of ASME Code Section III. NG-2000.
I Section 4.5.2.2 The welds of components for core support structures and reactor internals must be fabrisated in accordance with the ASME Code,Section III, NG-4000.
5.2.3 Reactor Coolant Pressure Boundary Materials.
Section 5.2.3.1 should satisfy Regulatory Guide 1.85; ASME Code Section II, Parts A, B, and C; ASME code Section III. Appendix I.
Section 5.2.3.2.2 should satisfy Regulatory Guide 1.44 and the ASME Code,Section III, NB-3120.
Section 5.2.3.3.1.1.3 This section describes an exception to Appendix G to 10 CFR 50. The reactor vessel beltline weldments in the test specimen will not necessarily corre from the actual production plate.
The applicant must submit a detailed explanation for the exception.
Section 5.2.3.4 should satisfy Regulatory Guide 1.36.
5.3.1 Reactor Vessel Materials The applicant should demonstrate that Section 5.3.1 satisfies GDC 1, 4, 14, 30.
and 31; Appendices Il and H to 10 CFR 50; and Regulatory Guides 1.37 and 1.65.
Sectio.n 5.3.1.3 must satisfy the requirements in Section Y of the ASME Code.
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2 Section 5.3.1.4 should satisfy Regulatory Guide 1.37, "Quality assurance Requirements for cleaning of Fluid Systems and Associate Cor@onents of Water-Cooled Nuclear Power Plants".
Section 5.3.1.5 is not detailed enough for the staff review. The applicant should demonstrate that Section 5.3.1.5 conforms to requirements of SRP 5.3.1.II.S.
5.3.1.6 Reactor Vessel Material Surveillance Program The applicant should discuss the chemistry or material content of base metal, weld metal, and heat-affected zone material. The copper, nickel, and phosphorus contents (in percentage) of each metal should be included.
The staff could not find Table 5.3-8 in Section 5.3.1.6.
5.3.1.7 Reactor Vessel Fasteners The applicant must specify the ultimate yield strength of the fasteners. The applicant must perfonn noncestructive examination (s) according to Section III of the ASME Code Subarticle NB-2580.
5.3.2.1 Limit Curves The applicant must discuss and satisfy the requirements for the pressure-temper-ature curves as described in 10 CFR 50 Appendix G.
For example the applicant should discuss that the minimum pemissible temperature is 60'F above the refer-ence temperature of tha closure flange regions that are highly stressed by the bolt preload.
The applicant should discuss and satisfy the requirements for the construction 1
of pressure-temperature curves per SRP 5.3.2.
Therefore, Section 5.3.2.1 should include all operating conditions as described in SRP 5.3.2.
This section should Thediscussionshouldincl$asdescribedinRekulatory also include a discussion on the calculation of RT the derivation of nitial Guide 1.99 Revision 2.
shif t, and margin of safety.
RTNOT RTNDT The pressure-temperature curves should be included in this section and not in chapter 16.
5.4.1.1 Pump Flywheel Integrity Pump flywheel integrity should satisfy the requirements in Regulatory Guide 1.14.
Paragraph 5.4.1.1c states that minimum fracture toughness of the flywheel materialwillbeequivalenttoadynamicstressintensiht> factor (KAlsohkragraph dynamic of at least 100 XSI/in (this unit should be written Ksi
).
of 45 5.4.1.1.C.2 uses a lower bound fracture toughress curve and dynamic KIC ksi/in [ sic) to comply to the minimun fracture toughness.
SRP 5.4.1.I.!!.2.
1 requires a mintroum static stress intensity factor of at least 150 Xsi/G and that the nontel operating temperature must be at least 100"? abov* the RTNDT'
1 3-The applicant should either a) use the requirements in SRP 5.4.1.1.II.2 verbatim, or b) justify that the stress intensity factors in paragraph 5.4.1.1.C satisfy the SRP requirements.
Paragraph 5.4.1.1.2.a should include the following statement "or 1/3 of the measured yield strength in the weak direction of the material f f appropriate tensile tests have been performed on the actual material of the flywheel."
Paragraph 5.4.1.1.2.b should state that the design overspeed of flywheel should be at least 10% above the highest anticipated overspeed.
The applicant s,hould either satisfy SRP 5.1.1.4.b requirements or justify paragraph 5.4.1.1.2.b.
Paragraph 5.4.1.1.2.c should include the following statement "or 2/3 of the measured yield strength in the weak direction of appropriate tensile tests have been perfonned on the actual material of the flywheel."
Paragraph 5.4.1.1.1.d should include the following statement "The ultrasonic examination of the areas of high stress concentration at the bore and keyway at about 31/3 years interval, during the refueling or maintenance shutdown coin-ciding with the inservice inspection schedule as required by the ASME code,Section XI.
Removal of the flywheel is not required."
g Paragraph 5.4.1.1.1.f should include the following statement "The liquid penetrant exarrination or magnetic particle methods and 100% volumetric examination by ultrasonic methods should be conducted at about ten years intervals during the plant shutdown coinciding with the inservice inspection schedule as required by the ASME Code,Section XI."
The applicant should review Section 5.4.1.1 to ensure it satisfies all require-ments in SRP 5.4.1.1.
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