ML18139C311

Submits Suppl to Relief Request from ASME XI Requirement Re 10-yr Inservice Insp Intervals.Suppl Supports Continued Insp & Would Eliminate Duplicative Insps

ML18139C311
Person / Time
Site:	Surry
Issue date:	04/14/1983
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Varga S Office of Nuclear Reactor Regulation
References
001B, 1B, NUDOCS 8304210424
Download: ML18139C311 (7)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS April 14, 1983 Mr. Harold R. Denton, Director Serial No. 001B Office of Nuclear Reactor Regulation NO/WDC:acm Attn: Mr. Steven A. Varga, Chief Docket No. 50-280 Operating Reactors Branch No. 1 License No. DPR-32 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

........ *_*.. "'-~::-*>~- .

SUPPLEMENT TO RELIEF REQUEST FROM ASME Xt REQUIREMENT SURRY POWER STATION UNIT NO. 1 10 YEAR INSERVICE INSPECTION Surry Power Station Unit 1 is currently performing its final inservice inspections for its first 10 year interval as required by ASME Section XI, 1974 Edition, Summer 1975 addenda (first 10 year interval governing code).

Pursuant to 10 CFR 50.55a paragraph g(5) and as a supplement to our letter dated January 7, 1983 (Serial No. 001), relief is requested from certain first interval, third period inspection requirements delineated in ASME Section XI.

The following basis is provided.

During the Surry Unit 1 steam generator replacement (9/14/80 7/6/81 inclusive) extensive preservice examinations were conducted to the requirements of IWB-2100 (74-S75 Code). Specific identification of components affected and the dates of the preservice examinations are provided on Enclosure 1. Due to the close proximity of the preservice examinations to the end of the third period, it is considered improbable that significant or relevant indications would be identified with an additional inspection in the third period.

Alternatively hydrostatic testing in accordance with IWB-5222 (77-S79 Code) is presently planned to fulfill the first interval requirements. All Class I components shall be visually examined under hydrostatic test pressure. In addition Surry Unit 1 has currently adopted the 1980 Edition, Winter 1980 addenda version of ASME Section XI. Inspections required by this code as supplemented by the Station's submitted relief requests will be conducted for the first period of the second interval.

8304210424 830414 PDR ADOCK 05000280 G PDR

e e V!ROINIA ELECTRIC AND PoWEli COMPANY TO Harold R. Denton It is our contention that approval of this relief request will not compromise the intended surveillance requirements of the code, but allow continued inspection under the rules of the 1980 Edition of ASME Section XI. This relief would eliminate the impractical duplication of simultaneous inspection under two different codes.

Very truly yours, Cx L, (~~-:>>~t W. L. Stewart Enclosure cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. J. Don Neighbors NRC Project Manager - Surry Operating Reactors Branch No. 1 Division of Licensing

e VIRGINIA ELECTRIC AND PoWEB COMPANY TO Harold R. Denton It is our contention that approval of this relief request will not compromise the -intended surveillance requirements of the code, but allow continued inspection 'under the rules of the 1980 Edition of ASME Section XI. This relief would eliminate the impractical duplication of simultaneous inspection under two different codes.

Very truly yours,

('\ I ,---

• U. L, --.2:.~->>~-

w. L. Stewart Enclosure cc: Mr. James P. O'Reilly Regional Acministrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. J. Don Neighbors NRC Project Manager - Surry Operating Reactors Branch No. 1 Division of Licensing

l

.LOSURE 1 REQUIREMENT PLANNED r*

COMPONENT STATION WELD NUMBER PRESERIVCE 3RD l:'ERIOD 1ST PERIOD CATEGORY ITEM IDENTIFICATION ISO (ENCL.) (IF APPLICABLE) AND DATE 1ST INTERVAL* 2ND INTERVAL B-F B3.3 'B' Steam VPA 05DM Vol - 4/9/81 Volumetric Volumetric generator 4200 Sur.- 4/9/81 Surface Surface safe end VT - 4/9/81 (Code percentage)

---

-------------- *---------~--------- -

_______ a _______

welds Vol - 5/13/81 Volumetric 06DM Sur.- 5/13/81 Volumetric Surface VT. - 5/13/81 Surface (Code oercentage)

Clad 'A' CP-1 VT - 4/2/81 Visual Visual .a Surfaces VPA CP-2 VT - 4/2/81 (Code percentage)~

B-I-2 B3.8 on au*

three steam 3100 'B' CP-3 VT - 4/2/81 Visual Visual generators CP-4 VT - 4/2/81 --~~~~=-percentage) __

'C' CP-5 VT - 4/7/81 Visual Visual CP-6 VT - 4/7/81 (Code percentage)

Socket welds 46 preservice Requires on charging, surface 4 addi- Surface B-J B4.8 reactor N/A N/A examinations tional (Code percentage) coolant, conducted welds to and safety (SGRP) those al-injection ready in-systems spected (Surface) e

SK ETCH S.HEET e e

. TOl<W 2A">77 WESTINGHOUSE ELECTRIC CORPORATION

. I

!LLUSTR.~TIVE ONLY STEA}li GEJ\!ERATOR

• WELD 1-1 = LOOP. 1

• WELD 2-1' = LOOP 2

• WELD 3-1 = LOOP 3 I '\

CP (Typ) r--------~ ~ n e l Head to 0-- Tube Sheet We1d-(Typ)

Mrn.

1

_5,. 16'

~--

CP (Typ) i Bo 1 ting * {Typ)

S.G. Manwa_y- Bal tine CP#

(1-RC-E-lA) 1 Hotside Al to A16 l (1-RC-E-lA) l Coldside A17 to A32 2

{1-RC-E-lB) 2 Hotside Bl to Bl 6 3 (1-RC-E-18) 2 Coldside B17 to B-32 4

{l -RC-E-1 C)

• 3 Hotside Cl to C-16 5 (1-RC-E-1C) 3 Coldside C-17 to C-32 6

• Replacement Weld installed Outage Core V-VI 1980-81.

'ESTINGHOUSc :.:..ECTRIC coloRATION VPA-1-4?00 1980 LOOP? RF.ACTOR COOLANT Pl PE R.C.

PUMP STEAM 6DM \

• GENERATOR

~11

\._21 1~ 7

\ " " - 10 9,J,, :8 20'"" ( t  :/,)6

.3f'RC5

--27.5.. RC6 NOTE: WELDS 18 THRU 21 ARE LONGITUDINAL ELECTROSLAG WELDS.

NOTE: WELDS 4~ 5DM, 6DM AND

. 7 REPLACED OUTAGE CORE V-VI 1980-81..

,L

_ .* . ~

ao--------

• W INGHOUSE ELECTRIC CORPO

~-------

TION VPA~l-41 00

~

1980

~

~

a:

0 u.

LOOP] REACTOR COOLANT PIPE R.C.

PUMP

.STEA.M 6DM~ GENERATOR

~n

\,,,'<.1 10

(

15 9\. ~ :B 7

20 t * :Y, 1e

. 3f'RC2

--27.E;'°RC3 NOTE: WELDS 18 THRU 21 ARE LONGITUDINAL ELECTROSLAG WELDS.

NOTE: WELDS 4,"SDM, 60M and *.

7* REPLACED OUTAGE CORE V-VI 1980-81.

,,.. **,