ML14266A349
| ML14266A349 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/18/2014 |
| From: | Mark D. Sartain Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 14-194A | |
| Download: ML14266A349 (4) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 18, 2014 10 CFR 50.55a United States Nuclear Regulatory Commission Serial No.
14-194A Attention: Document Control Desk NL&OS/GDM RO Washington, D. C. 20555 Docket No.
50-281 License No.
DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 FIFTH 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM AND ALTERNATIVE REQUESTS RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION SYSTEM PRESSURE TEST OF BOTTOM OF REACTOR VESSEL By letter dated May 7, 2014 (Serial No.14-194), Virginia Electric and Power Company (Dominion) submitted the Inservice Inspection (ISI) Program for the Fifth 10-Year Inservice Inspection Interval for Surry Power Station (Surry) Unit 2 for Class 1, 2, and 3 Components and Component Supports.
The letter included Relief Request S2-15-SPT-01, "System Pressure Test of Bottom of Reactor Vessel," that proposed an alternative to the ASME Section Xl requirement to perform a visual (VT-2) examination of the bottom of the reactor vessel during the system leakage test.
On August 27, 2014, the NRC Project Manager for Surry transmitted a request for additional information to facilitate NRC staff review of the proposed alternative.
Dominion's response to the NRC request is provided in the attachment.
If you have any questions or require additional information, please contact Mr. Gary D. Miller at (804) 273-2771.
Respectfully, Mark D. Sartain Vice President - Nuclear Engineering Commitments made in this letter: None
Attachment:
Response to NRC Request for Additional Information, Relief Request S2-15-SPT-01, System Pressure Test of Bottom of Reactor Vessel
/3(4F1
Serial No. 14-194A Docket No. 50-281 Page 2 of 2 cc:
U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector Surry Power Station Ms. Karen Cotton, NRC Project Manager - Surry U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G9A 11555 Rockville Pike Rockville, Maryland 20852 Dr. V. Sreenivas, NRC Project Manager - North Anna U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G9A 11555 Rockville Pike Rockville, Maryland 20852 Mr. R. A. Smith Authorized Nuclear Inspector Surry Power Station
Serial No. 14-194A Docket No. 50-281 Attachment Response to NRC Request for Additional Information Relief Reauest S2-15-SPT-01. System Pressure Test of Bottom of Reactor Vessel Virginia Electric and Power Company (Dominion)
Surry Power Station Unit 2
Serial No. 14-194A Docket No. 50-281 Attachment Response to NRC Request for Additional Information Relief Request S2-15-SPT-01, System Pressure Test of Bottom of Reactor Vessel Surry Power Station Unit 2 By letter dated May 7, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML14133A006), Virginia Electric and Power Company, submitted for staff review and approval ISI Program Alternative Request S2-15-SPT-01 which requests an alternative to the ASME Section Xl code requirement of subarticle IWB-5220 for the Class 1 system pressure test of the bottom of the reactor vessel. To complete its review, the staff requests the following additional information.
- 1. The May 7, 2014 submittal states that the visual examination (VT-2) of the bottom of the reactor vessel will be "conducted as soon as conditions allow entry into the in-core area." What are the reactor coolant system temperature and pressure expected to be when the visual examination (VT-2) is conducted?
Response
The reactor coolant temperature and pressure are expected to be between 100 and 200 degrees F and 300 to 340 psig, respectively, when the VT-2 examination is conducted.
- 2. Is the reflective metal insulation on the bottom of the Unit 2 reactor vessel still as described in the email response to the NRC request for additional information related to Relief Request SPT-003 dated November 19, 2010 (ADAMS) Accession Number ML103280015)?
Response
The insulation on the bottom of the Unit 2 reactor vessel remains as described in the email response to the NRC request for additional information related to Relief Request SPT-003 dated November 19, 2010.
- 3. The May 7, 2014 submittal states that the visual examination (VT-2) is conducted in accordance with ASME Section X1 IWA-5242(a),
(b) and (c).
10 CFR 50.55a(b)(2)(xxvii) requires the removal of insulation from bolted connections containing certain 17-4 PH or 410 stainless steel studs or bolts when performing examinations in accordance with IWA-5242. Are there any bolted connections at the bottom of the Surry Unit 2 reactor vessel to which this requirement would apply?
Response
There are no pressure retaining bolted connections on the Surry Unit 2 reactor vessel bottom area.
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