ML20082T185
| ML20082T185 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 12/09/1983 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| References | |
| 647, NUDOCS 8312150211 | |
| Download: ML20082T185 (5) | |
Text
'h.
o' VIRGINIA ELECTPIC AND Powan COMPANY RrcxxoNn, VIRGINIA 23261 W.L.SrawAmr Vacs Pa..un.wr December 9, 1983 w ca. min or.uio,.
Mr. Harold R. Denton, Director Serial Noe 647 Office of Nuclear Reactor Regulation N0/WDC:acm Attn:
Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 1 50-281 U. S. Nuclear Regulatory Commission License Nos. DPR-32 Washington,'D. C. 20555 DPR-37 Gentlemen:
During the recent Surry Unit I and Unit 2 outages, certain ASME,Section XI requirements were modified due to conditions which either prevented completion or provided extremely difficult circumstances.
Pursuant to 10CFR 50.55a, paragraph g(5), relief is requested from these certain code requirements as delineated in ASFB,Section XI.
The following basis is provided.
1.
. Surry Unit 1; As part.of the first 10 year ASME,Section XI inservice inspection program, 1974 Edition, Summer 75 Addenda, the non-regenerative letdown heat exchanger (1-CH-E-2) integrally welded support (2ws) required 100% surface examination as delineated in category C-E-1 and item C2.5 of table IWC-2600. 'Surry's ASME, Class 2 examination program was initiated in 1980 after the construction preservice require nents.
Visual examination-of the support confirmed the need for extensive weld preparation. prior to the surface inspection.
Radiation levels (Attachment 1) located beneath the heat exchanger, were measured to 30R requiring shielding to reduce levels (Attachment 2).
The lead shielding in combination with numerous physical obstructions associated with the heat exchanger structure prevented the weld preparation in some areas.
As a result, approximately 75% -of weld was inspected (31guid penetrant) revealing no rejectable indications.
The remaining 25% could not be
' inspected because of the preparation problems.
We contend that adequate insurance of weld integrity has been assured, and that the situatiou justified the rcduced examination.
2.
Surry Unit 2; As required.by IWA 4400(a) of ASME,Section XI, 1980 Edition, Winter 80 Addenda, following the welded installation of 2-MS-76, a post repair hydrostatic test was attempted.
The ils inch valve (Attachment 3) is ASME, Class 2 functioning in a drain capacity within the main steam system.
Hydrostatic test requirements are defined in IWC-5222(a) of ASME,~Section XI.
From this paragraph a test pressure of 1356 psig is derived.
In attemptirg to attain the required pressure, boundary valve isol.ation leakage was evident.
A test pressure of 1210 psig was reached using the stations auxiliary feedwater pump.
The internal leakage of the boundary valves prevented full pressurization.
w w w ik 8o't$
+
i Vamonnu Exactasc Awo Powna CourAny to Harold R. Denton
-Secondary-~ isolation 'was impractical, as evidenced by the attached drawing, requiring full pressurization of the steam generator.
A VT-2 examination-was; conducted' at 1210 psig.
In. addition, a surface examination -(liquid ~ penetrant) vis conducted on the replacement. welds -
arevealing no reportable indications.
u
'. We feel adequate ~ testing. has been accomplished, noting that 89% of test
- pressure was achieved.
The additional surface examination was not code-required.n but1 administrative 1y required by; the station adding - insurance of weld integrity.-
- These -relief ~ requests _ serve. as our notification of deviations from ASME,Section XI.
Notification prior to'the deviations was not possible as there
.was no anticipation of the problems or their extent.
V y truly.yours,
\\
4 bS W. L. Stewart cc:- Mr. James P. O'Reilly
' Regional Administrator Region-II
'Mr._J. D. Neighbors Project Manager-Surry Operating Reactors Branch No. 1 Division of: Licensing
'lir. D. J. Burke NRC Resident Inspector Surry Power Station e
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