ML20063F898
| ML20063F898 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 08/25/1982 |
| From: | Wuller G ILLINOIS POWER CO. |
| To: | Bernard H Office of Nuclear Reactor Regulation |
| References | |
| U-0530, U-530, NUDOCS 8208310379 | |
| Download: ML20063F898 (2) | |
Text
.
U-0530 ILLIN0/S POWER COMPANY f"gg, 739_ggz99_g5yg 500 SOUTH 27TH STREET, DECATUR, ILLINOIS 62525 august 25, 1982 Mr. Harold Bernard, Acting Chief Standardization & Special Projects Branch Division of Licensing Office of Nuclear Reactor Regulation U.
S.
Nuclear Regulatory Commission Washington, D.C.
20555
Reference:
IP letter - 1/13/82, U-0349, Compliance to NRC Regulations, G.
E. Wuller, IP to J.
R. Miller
Dear Mr. Bernard:
Clinton Power Station Unit 1 Docket No. 50-461 The referenced letter transmitted the Illinois Power Company report on demonstration of compliance to NRC regulations for the Clinton Power Station Unit 1.
Recently it was brought to our attention by Mr.
H.
H. Livermore, NRC Resident Inspector, that there was an error on page 16 of that report wherein we inadver-tently referenced an incorrect addenda of the ASME Boiler and Pressure Vessel Code for the reactor coolant system piping.
Attached is a revised page 16 of the referenced report which identifies the changes and corrects the error made in the original issue.
Sincerely, f
G.
E. Wuller Supervisor - Licensing Nuclear Station GEW/j a Enclosure cc:
Mr. J. H. Williams, NRC Clinton Project Manager Mr.
H.
H.
Livermore, NRC Resident Inspector Illinois Dept. of Nuclear Safety (W/ Complete & Corrected Reference (3 ) document. )
QDDI 8208310379 820825 DR ADOCK 05000461 PDR
Revised September 24, 1982 10 CFR Regulation Comnliance 50.54 Much of 50.54 provides that other provisions of the cont'd.
law apply.
FSAR Subsection 13.5.1.3 references procedural compliances to this regulation.
50.55 This regulation addresses conditions of construction permits, not operating licenses, and so it is not relevant for OL review.
50.55a(a)(1)
Various Chapters of the FSAR discuss design, fabrication, erection, construction, testing, and inspection of safety related equipment.
For example, Chapter 14 provides information on testing of safety related systems.
Chapter 17 provides information concerning the Quality Assurance Program.
As a further example of a specific system, Chapter 5, Section 5.2, " Integrity of the Reactor Coolant System Boundary", discusses the design of the reactor coolant system.
FSAR Subsection 5.2.1.1 establishes compliance with 10 CFR 50.55a.
50.551(a)(2)
This paragraph is a general paragraph leading into paragraphs (c) through (i) of the regulation.
50.55a(b)(1)
These paragraphs provide guidance concerning the 50.551(b)(2) approved Edition and Addenda of Sections III and XI of the ASME B&PV Code.
50.55a(c)
Design and fabrication of the reactor vessel was carried out in accordance with ASME Sections III and i
IX, 1971 edition, summer 1973 addenda of the ASME Boiler and Pressure vessel Code, Class 1.
Information can be found in Subsection 5.3 50.55a(d)
Reactor coolant system piping meets the requirements of ASME Sec. III 1974 Edition, Summer 1974 Addenda.
Information can be found in Chapter 5, Subsection
- 5. 4. 3 and 3. 9. 3.1.1.10 of the FSAR.
l 50.55a(e)
Reactor Coolant pumps meet the requirements of ASME I
III 1971 Edition, Winter 1973 Addenda, Class 1.
Information can be found in Chapter 5, of the FSAR.
50.55a(f)
Based upon the construction permit date of Feb. 24, 1976, the valves within the Reactor. Coolant System pressure boundary were ordered and supplied in accordance with the requirements of ASME Sec. III._