ML18151A102
| ML18151A102 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/06/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 87-630, NUDOCS 8710130260 | |
| Download: ML18151A102 (4) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS October 6, 1987 U. S. Nuclear Regulatory Connnission.
Attn:
Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 ASME SECTION XI RELIEF REQUEST FROM HYDROSTATIC PRESSURE TEST REQUIREMENTS Serial No.87-630 NO/ISI License No. 50-280 Docket No. DPR-32 Surry Unit 1 is performing a replacement within a system designated as ASME _Class 2.
Pursuant to 10CFR50.55a(g)(5), relief is requested from certain post replac~ment test requirements delineated in ASME Section XI.
The following basis is provided.
A four inch isolation valve (l-MS~86) located in the main steam system requires replacement.
The valve experienced a
body-to-bonnet leak, requiring temporary repair.
Surry Unit 1 is currently in an unplanned outage which began October 2, 1987.
Restart is scheduled for October 7, 1987.
The current outage allows replacement, which offers a permanent solution.
A failure analysis is being conducted at this time on the original valve.
This replacement as defined in IWA:-5214 requires a hydrostatic pressure test in accordance with IWC-5222 in ASME Section XI, 1980 Edition through the Winter 1980 Addendum.
This pressure test would encompass "A"
Steam Generator* and a
large section of attached main steam piping within the test boundary, as shown by the attached drawing.
This test is considered extremely difficult and impractical.
As an alternative, it is proposed that a surface examination (liquid penetrant) be performed on the final welds.
In addition, a
system pressure test (IWC-5221) in conjunction with a VT~2 examination wil~lbeo performed.
~
,,J{ ~,~~
1 a710l30260 B0~l,8&ts~
I. PDR. A_DO~K
.
- PDR D
... *. \\
\\
P Lo
This request is identical to a previous request submytted by us on March 26, 1984 and approved by the NRC on May 17, 1984.
It is our op1n1on that adequate alternative examinations provide the Code.
relief basis is provided and that the necessary inspections intended by the In accordance with 10CFR170, and application fee of $150.00 is enclosed.
Very truly yours, Attachment
e cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident.-Inspector Surry Power Station
)
STEAM /
GENERA Tll!S 1-RC-E-IA e
y 1M CAP ON EACH HEADER TD BE SHIPPED LOOSE FOR FIELD
'ELDING PRIOR TD CIIEIIICAI. Q.EANING.
4"-SHP-27-601 l
Z"-Qf-25-601 IFll-148 II H-31 REFERENCE DRAIINCS:
now DIAGIIAII STEAM GENERATOR 111.0IDOIIN now DIACIWI,m STEAM.. AIR RElllVAI. SH, now DIAGIIAII COffAINlNl.. RECJRC._ SPRAY now DIACIWI SAIA. ING SYSTEM
. now DIAGRAM 111sc. DRAINS-SECOCIARY Pl.AH now DIAGRAM TIIIBINE Gt.AND STEAM now DIAGRAM EXTRACTION STEAM VALVE IJ'ERATING IUIIERS IIAIN STEAIII now DIACIWI STEAM GEN, NITROGEN CONN.
now DIAGRAM COAIESSED AIR SYSTEIIISHT,4 1-l\\IS-86.
6' TD AUX.
i I
0 'f.. '
N lC Ii Li Ill a L
1 Z"-SHP0-7-601