ML18143B653
| ML18143B653 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/11/1985 |
| From: | Thompson H Office of Nuclear Reactor Regulation |
| To: | Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| TAC-59754, NUDOCS 8510180183 | |
| Download: ML18143B653 (14) | |
Text
Docket No. 50-281 MEMORANDUM FOR:
FROM:
SUBJECT:
e October 11, 1985 Roger D. Walker, Director Division of Reactor Projects Region II Hugh L. Thompson, Jr., Director Division of Licensing Office of Nuclear Reactor Regulation LICENSING ACTION REVIEWS FOR SURRY POWER STATION, UNIT 2 - ASME XI INSPECTION RELIEF REQUEST (TAC 59754)
Your assistance is requested in conducting a review of the enclosed submittal from the Virginia Electric and Power Company (VEPCO), dated September 19, 1985, for Surry Power Station Unit 2.
The product expected from you as a result of your review is a complete safety evaluation report.
Your reviewers should use the Standard Review Plan (SRP) and Standard Technical Specifications (STS) as guidance in determining acceptance criteria, recognizing, of course, that for operating reactors, the criteria in these documents are not requirements.
In accordance with NRR Office Letter No. 44, each safety evaluation performed by a technical division shall have a separate SALP input.
For purposes of these reviews, the Regional personnel involved are considered part of the technical divisions. Therefore, we are requesting that your forwarding memorandum contain a SALP input for the safety evaluation.
Work for the VEPCO submittal concerning the proposed changes has been discussed with D. Gruber of your staff. The TAC number for this review is 59754.
The requested completion date is November 30, 1985.
Contact with the licensee on this review effort or any significant additional information deemed necessary should be obtained through the NRR Project Manager or with his concurrence.
The Project Manager for this plant is Terence Chan and he can be reached at 492-8460.
~
Miraglia/to~
Hugh L. Thompson, Jr., Director Division of Licensing Office of Nuclear Reactor Regulation
Enclosure:
As stated CONTACT *.
8510190193 851011 PDR ADOCK 05000291 T. Chan G
PDR (301) 492-8460
- ORB#l:DL O~L CParrish TChan;ps 10/ 9 /85 10/ 1 /85 ~
e!Ji85
- See next~page for concurrence ADi_R:DL GL'.ainas 10/1( /85
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Docket No. 50-281 Distributionw/o encl.
Docket file ORB#l ROG MEMORANDUM FOR:
Roger D. Walker, Director Division of Reactor Projects Region II NRC PDR LPDR Memo file HThompson CParrish FROM:
SUBJECT:
Hugh L. Thompson, Jr., Director Division of Licensing Office of Nuclear Reactor Regulation T. Chan w/encl.
LICENSING ACTION REVIEWS FOR SURRY POWER STATION, UNIT 2 - ASME XI INSPECTION RELIEF REQUEST (TAC 59754)
Your assistance is requested in conducting a review of the enclosed submittal from the Virginia Electric and Power Company (VEPCO), dated September 19, 1985, for Surry Power Station Unit 2.
The product expected from you as a result of your review is a complete safety evaluation report.
Your reviewers should use the Standard Review Plan (SRP) and Standard Technical Specifications (STS) as guidance in determining acceptance criteria, recognizing, of course, that for operating reactors, the criteria in these documents are not requirements.
In accordance with NRR Office Letter No. 44, each safety evaluation performed by a technical division shall have a separate SALP input.
For purposes of these reviews, the Regional personnel involved are considered part of the technical divisions. Therefore, we are requesting that your forwarding memorandum contain a SALP input for the safety evaluation.
Work for the VEPCo submittal concerning the proposed changes has been discussed with D. Gruber of your staff. The TAC number for this review is 59754.
The requested completion date is November 30, 1985.
Contact with the licensee on this review effort or any significant additional information deemed necessary should be obtained through the NRR Project Manager or with his concurrence.
The Project Manager for this plant is Terence Chan and he can be reached at 492-8460.
Enclosure:
As stated CONTACT:
T. Chan (301) 492-8460\\
ORB#l:DL~
CParri sh \\j 10/0\\/85 Hugh L. Thompson, Jr., Director Division of Licensing Office of Nuclear Reactor Regulation BC-ORB#l:DL SVarga AD:OR:DL GLainas 10/ /85 D:DL HThompson 10/ /85 10/ /85
e e
R(GULAT~R) lN~OR~ATlO~ ~JSlkTbUTIUN SYSlfM (Rln~)
ACCESSION NtiR:850924010.l Due.DAT[: B~/09/19 NOTARIZED:,~o LiOCKET ti fACIL:50*281 Surfy Power Station, Unit 2, ~irginia Electric~ Pow~
0~000281 AUTrl.~AME' AUTHUR AFF1L1ATI0N STE~ARl,~.L.
Virginid Power (Virginia ~1eetrie & Power Co.)
RECIP.NAME HECI~I~NT AF~ILIATIO~
DENTON,H,R.
Office of Nuclear Reactor Regulation, Director vARGA,S.A, Operating Reactors Branch 1 SUt,JE.CT: Requests relief from certain ASME. Boiler, Pressure Vessel Code,Section ~I requirenients,per 10CFR50.55Ca),~ases tor request discussed.
DlSTRI~UTluN CODt: Aoq/D COPIES RtCE.lVED:LTR _/ENCL~
SIZE: ____././_ __ _
TITLE: OR Submittal: Inservice Inspection/Testing
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e V*IRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIROINIA 23261 September 19, 1985
'\\\\'. L. STEWART VICE PRESIDENT Nee.LEAB OPERATIONS Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No.
Division*of Licensing U;S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 ASHE XI - INSPECTIOll RELIEF REQUEST Serial No.85-681 NO/WRB:cfm Docket Nos.
50-281 1
Licensee Nos.
DPR-37 Inservice inspection activities for Surry Unit 2 were*conducted during the spring refueling outage as required by Section XI of the ASHE Boiler and Pressure Vessel Codes.
Pursuant to 10 CFR 50.55a paragraph g(5) relief is requested from certain code requirements. The follo~ing bases are provided.
- 1. The regenerative heat exchanger (2-CH-E-3) is classified ASME Class 1 in the first interval inspection plan (ASME
- XI 74 edition, Summer 75 addenda).
The following items were scheduled per table IWB-2600 to b,e completed during the refueling outage on the regenerative heat exchanger (Regen Hx):
Table IWB-2600 Table IWB-2500 Parts to be examined Method Item No.
.* Examination Category (attachment 1)
B3.l B3.l B3.2 B-B B-B B-D Head to shell weld(17) Volumetric Shell to tube sheet Volumetric weld(18)
Nozzle to vessel
- substituted welds(5,6,7,8,9 surface 10,11,12,14, and
- 16)
- On February 28, 1984, Vepco was granted relief (letter Mr. Varga to Mr. Stewart)to substitute a surface exam for the required yolumetric method due to the impractical joint configuration that exists.
-8509246 lot &50919 PDR ADOCK 05000281 G
VIRGINIA ELEcrn1c AND PowEE-CoMPANY To Mr. Harold R. Denton The seal water return filter (2-CH-FL-3) is classified ASME Class 2 in the first interval inspection plan (ASME XI 74 edition, Summer 75 addenda).
The following items were scheduled per table IWC-2600 to be completed during the refueling outage on the seal water return filter:
Table IWC-2600 Table IWC-2500 Parts to be examined Method Item No.
Examination Category (attachment 2)
Cl. I C-A I" head to shell
- substituted weld(2) surface and visual Cl. I C-A l" top head weld(3) *substituted surface and visual Cl. 3 c-c Welded support (IWS) surface
- On February 28, 1984, Vepco was granted relief (letter Mr.
Varga to Mr. Stewart) to substitute surface and visual exams for the required volumetric due to the thin structure of the associated materials, reducing.the effectiveness of a volumetric exam.
Preinspection meetings with the Health Physics Department determined that unreasonable doses would result from completion of these examinations.
The close quarters surrounding these components limit shielding and allow effective us:e of only one individual to remove
.insulation (Regen Hx only), perform necessary surface preparation, perform the inspection, and reinsulate (Regen Hx only).
In addition surface preparation time can be extended significantly as a result of the limited preservice examination requirements associated with the earlier codes.
In many cases this has left these type of welds in poor surface condition for examination.
V1uonnA ELECTRIC AND PoWE:a,CoMPANY To Mr. Harold R. Denton The seal water return filter (2-CH-FL-3) is classified ASME Class 2 in the first interval inspection plan (ASME XI 74 edition, Summer 75
-addenda).
The following items were scheduled per table IWC-2600 to be completed during the refueling outage on the seal water return filter:
Table IWC-2600 Table IWC-2500 Parts to be examined Method Item No.
Examination Category (attachment 2)
Cl.1 C-A 1
11 head to shell
- substituted weld(2) surface and visual Cl.1 C-A 1" top head weld(3) *substituted surface and visual Cl.3 c-c Welded support (IWS) surface
- On February 28, 1984, Vepco was granted relief (letter Mr.
Varga to Mr.
Stewart) to substitute surface and visual exams for the required volumetric due to the thin structure of the associated materials, reducing the effectiveness of a volumetric exam.
Preinspection meetings with the Health Physics Department determined that unreasonable doses would result from completion of these examinations.
The close quarters surrounding these components limit shielding and allow effective use of only one individual to remove insulation (regen.
only),
perform necessary surface preparation, perform the inspection, and reinsulate (regen. only).
In addition surface preparation time can be extended significantly as a result of the limited preservice examination requirements associated with the earlier codes. In many cases this has left these type of welds in poor surface condition for examination.
e VIRGINIA ELEcTn1c AND Po""ER CoMPANY To Mr. Harold R. Denton The following estimated doses are provided for each component examination (assuming average weld preparation time):
Regenerative Heat Exchanger 7000 mr/hr Contact 3000 mr/hr 12 inches 400-1400 mr/hr general area TASK Insulation Removal Weld Preparations Inspection Reinsulation TOTAL Seal Water Return Filter MAN HOURS 3
3 2
3 11 2000 mr/hr Contact 15 man-rem (estimate)
(general area unknown)
TASK Weld Preparations Inspection TOTAL MM HOCRS 1
2 3
6 man-rem (estimate)
As an alternative, it is requested that the normal hydrostatic pressure tests be accepted in lieu of the previously described examinations.
These hydrostatic pressure tests were successfully completed in conjunction with their VT-2 examination as follows:
Component Date test Completed Regen Hx (charging side)
June 4, 1985 Regen Hx (letdown side)
June 30, 1983 Seal Water Return Filters May 2, 1985 Test Pressure 3427 psig 2340 psig 192 psig Acceptance.of this relief request would greatly reduce exposure of personnel and would be commensurate with our ALARA practice..
- --,~-
VIRGINIA ELEcTBic AND PowEa CoMPANY To Mr. Harold R. Denton
- 2. The residual heat removal return isolation valve (MOV-RH-2720B) is classified ASHE Class 1 (attachment 3). A Table IWB-2600, (ASME XI 74 edition, Summer 75 addenda) item B6.7, category B-M-2, valve internal visual inspection was required this refueling outage.
A substituted thickness measurement examination from the exterior wall was attempted.
This atlernative was approved by relief request on January 24, 1984 (letter Mr. Varga to Mr. Stewart), relief request SR-1.
As noted by the attached inspection form (attachement 4), accurate thickness readings could not be achieved. By previous agreement (phone conversation Mr. Neighbors et al, NRC and Mr. Hegner et al, Vepco, March 21, 1985) relief from the thickness measurement requirement would be addressed on an individual basis.
Therefore,* it is requested that acceptance of the system hydrostatic pressure test be allowed as the alternative examination requirement.
These tests,(Class 1 to Class 2 boundary valve) were completed with the associated VT-2 examinations on July 1, 1983 and April 22, 1985 at test
.pressures of 600 psig and 750 psig, respectively.
It is our opinion that acceptance of this relief request provides the most practical resolution to the examination difficulties presented.
- 3. The current code edition, AS:-IB Section XI 1980 edition, Winter 1980
- addenda, states in paragraph IWA-7210(a) that replacement components shall meet the original construction code requirements or, alternatively, the requirement of IWA-7210(c).
IWA-7210(c) states that replacements may meet the requirements of later editions of the construction code (in this case USAS B-31.1 - 1967), providing any additional requirements are met and that the later edition has been approved by the NRC.
No later editions of USAS B31.1 were approved by the NRC for nuclear work in 10 CFR 50.55a limiting Surry, under the rules of ASME Section XI, to the original code in power piping/component type replacement. It is requested that the use of ASME Section III be permitted in the same context that paragraph IWA-7210(c) above is intended for later editions of the original construction code for these types of replacements. Use of. ASME Section III as approved by the NRC, allows the use of more "state of the art" requirements and provides more flexibility in our repair/replacement program.
L-
V1B01NIA ELECTRIC A1D PoWER.CoMPANY To Mr. Harold R. Denton Specific use of this relief was already applied during the outage in the replacement of 2-SI-338, a 2 inch ASME Class 2 manual valve (attachment 5), used in setting flow for the high head safety injection syst~m.
Procurement of a valve meeting the original construction code and nuclear code cases could not be made, however the original manufacturer stocked a valve, which met ASME Section III NC requirements, except for stamping and met the requirements of ASME Section XI, IWA 7210 (c) as discussed.
It is our opinion that this request is administrative only, but acceptance is necessary to fully comply with the code requirements.
We also feel that adequate bases for the relief requested herein have been presented above, and that Surry will continue to meet, with the alter~ative proposals, the integrity assurance intended by the code.
Very truly yours,
"\\\\~----
_-'\\
~~~
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w: L. Stewart Attachments cc:
(w/attachment)
Mr. T. L. Chan
~"RC Project Manager - Surry Operating Reactors Branch No. 1 Division of Licensing.
Mr. D. J. Burke NRC Resident Inspector Surry Power Station
I
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