ML18153B071
| ML18153B071 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/12/1994 |
| From: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 94-414, NUDOCS 9409200075 | |
| Download: ML18153B071 (12) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 12, 1994 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 Serial No.94-414 SPS/ETS Docket No.
50-280 License No.
DPR-32 THIRD INTERVAL INSERVICE INSPECTION PROGRAM ADDITIONAL INFORMATION REQUEST Your letter (Serial No.94-414, dated June 8, 1994) requested additional information concerning the Surry Unit 1 third interval ISi program. This additional information has been provided in Attachment 1 to this letter.
As a result of our review of the information requested and recent ASME Code developments, Relief Request 4 (concerning hydrostatic testing of the component cooling water system) is no longer deemed necessary and is withdrawn. With the recent ASME approval of Code Case N-498-1, Alternative Rules for 10-Year System Hydrostatic Testing for Class 1, 2, and 3 Systems and the relatively long duration of time before applicable third interval testing is required, adequate time should be available to permit endorsement of this Code Case through the normal Regulatory Guide 1.147 revision process. If this issue has not been resolved by the time 10-year testing is required, separate correspondence will be submitted for the specific areas needing relief.
Should you have any questions or require additional information, please contact us.
Very truly yours,
!:t.~6~
Senior Vice President - Nuclear Attachment
,.---~--------
9409200075 940912 PDR ADOCK 05000280 Q
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cc:
U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
Atlanta, Georgia 30323 Mr. Morris Branch NRC Senior Resident Inspector Surry Power Station
A. NRC:
ATTACHMENT 1 ADDITIONAL INFORMATION REQUESTED ON SURRY UNIT 1 THIRD INTERVAL ISi PROGRAM Table IW8-2500-1, Examination Category 8-G-1, Note 3, requires selection of bolting on heat exchangers, piping, pumps, and valves for examination be limited to those components selected for examination under Examination Categories 8-8, 8-J, 8-L-2, and 8-M-2.
In review of pump bolting selected for inspection, the staff noted that the pump bolting selection was associated with 8-L-1 versus 8-L-2, as the 89 Edition of Section XI requires.
Please provide clarification and/or technical justification regarding the above discrepancy.
Response
The Code requires that the bolting selected for Category 8-G-1 examinations coincide with the pump selected for examination under Category 8-L-2. This was not indicated in the plan for the following reasons:
a)
Category 8-L-2 requires a visual VT-3 examination of our Class 1 reactor coolant pump casing internal pressure boundary surfaces, when one of the pumps is disassembled for maintenance, repair
-or volumetric examination. It was not known at the time of the plan development, which, if any, of the reactor coolant pumps would be disassembled for maintenance or repair.
b)
Surry Unit 1 also uses Code Case N-481, Alternate Examination Requirements for Cast Austenitic Pump CasingsSection XI, Division 1.
This has eliminated the possibility of pump disassembly due to the volumetric examination requirement of Category 8-L-1.
c)
Code personnel were contacted regarding pump bolting inspections if a pump was not dissambled for inspection (8-L-2) during the interval. In the opinion of the committee members, it was not the Code's intent to eliminate the bolting examination requirements if a pump was not disassembled over the interval.
Therefore, a set of pump bolts was included in the plan to ensure that the examination was performed.
If pump disassembly occurs, the plan will be modified to indicate that bolting examinations were performed on the disassembled pump.
Otherwise, the pump identified in the plan will receive the required bolting examination to satisfy Category 8-L-2.
B. NRC:
e Paragraph 1 O CFR 50.55a(b)(2)(iv) requires that appropriate ASME Code Class 2 piping welds in the Residual Heat Removal (RHR),
Emergency Core Cooling (ECC), and Containment Heat Removal (CHR)
Systems be examined. The staff believes that piping welds in these systems should not be completely exempted from inservice volumetric examination based on Section XI exclusion criteria contained in Table IWC-2500-1.
In the review of Class 2 piping welds selected for examination, the staff noted that a significant number of welds in the Containment Spray and Safety Injection _Systems are excluded from examination based on wall thickness. For example, all welds in the Containment Spray System
{CSS) on the discharge side of the containment spray pumps have been excluded from examination. The CSS piping on the discharge side of the pumps is a critical part of the system that is relied on to function during emergency conditions. This portion of the CSS contains stagnate oxygenated borated water, which has been found to be a major contributor to lntergranular Stress Corrosion Cracking in stainless steel piping. To provide assurance of the structural integrity of the thin-walled welds, the NRC recommends that Licensees perform an augmented volumetric examination on a small percentage, specifically 7.5% of welds in those portions of lines excluded from examination. The licensee is requested to address this concern.
Response
The selections of Class 2 piping welds meet and exceed the requirements of Table IWC-2500-1. The Code requires in note 2(a)
(Category C-F-1) that the selected welds be prorated by the number of nonexempt welds in a system. This would allow some systems to have less than 7.5% of the nonexempt welds selected for that system. The selection at Surry used the code requirements, and then increased any system with less than the 7.5% up to that amount without reducing the other weld selections. The selections were made on welds (C5.1 O) 0.375 inch wall-thickness or greater as required by the Code.
The Containment Spray and Safety Injection Systems have enough welds of
>0.375 inch thichness to meet the Code selection requirements or the system limitation of 7.5% of the nonexempt welds, which ever was more.
The Containment Spray (CSS) System distribution of selections are located rn the suction piping as a result of using the Code required 0.375 inch wall-thickness limitation. However, weld 1-19 on line 8"-CS-34-153 is scheduled for a PT/UT (surface/volumetric) examination to meet Surry's Technical Specification augmented inspection requirements for sensitized stainless steel. This weld is located on the discharge side of containment spray pump, 1-CS-P-1 B.
Additionally, one of the welds selected on the suction side of the pumps will be replaced with one selected on the discharge side of 1-CS-P-1A. This weld will receive a volumetric and surface examination. The Code requirements would be maintained.
C. NRC:
e The Safety Injection (SI) System does include both suction and discharge selections. However any thin-walled piping was not selected again, because of the Code required >0.375 inch wall-thickness limitation in item C5.10.
Two additional welds will be selected on certain thin-walled (<0375 inch)
SI piping.
These welds will receive a volumetric and surface examination. All Code requirements would be maintained.
Relief Request SR-003: Examination Category B-D, Item B3.120 requires a 100% volumetric examination of the nozzle inside radius section of the pressurizer nozzles.
The Licensee proposes a visual (VT-2) examination of the pressurizer surge line nozzle area to be performed during the normally scheduled pressure test (Class 1) each refueling outage.
Paragraph IWA-2240, "Alternative Examinations", of the ASME Code Section XI states, "Alternative examination methods, a combination of methods, or newly developed techniques may be substituted for the methods specified in this Division, provided the Inspector is satisfied that the results are demonstrated to be equivalent or superior to those of the specified method." The above mentioned Code-required examination (VT-2 visual during pressure test) is not considered an alternative examination.
Please provide additional information or an alternative examination that will ensure operational readiness of the subject examination areas.
Response
The Code requires a volumetric examination of the pressurizer surge nozzle's inside radius section.
The relief request details the impracticality of performing an ultrasonic examination.
The same impracticality would exist for radiographic examinations with additional configuration constraints for film and source placements. A surface examination would again require significant preparation to access the area in question, and would not address the inside radius section of the surge nozzle.
An I.D. visual (VT-1) examination is considered impractical, since the area in question is covered by a welded retaining basket. This basket has only 3/8 inch (nominal) holes, making any penetration into the area of interest extremely difficult. Additionally, the area is partially covered by a thermal sleeve (drawing attached).
The visual (VT-2) examination is the only practical Code examination that may be performed. The integrity of the nozzle is additionally monitored in accordance with Technical Specifications, which requires leak rate monitoring of the Reactor Coolant System through calculation and radionuclide detection means.
The nozzle's inside radius sections located on the top head of the pressurizer will receive a Code examination, which provides an assurance of integrity from a sampling perspective. As such, it is our position that sufficient alternatives to the
e Code requirements exist to monitor the integrity of the pressurizer surge nozzle.
D. NRC:
Relief Request SR-005: The existing calibration blocks at Surry Power Station, Unit 1, were designed and fabricated before guidelines of ASME Section XI were developed and approved. Please provide a list of the ultrasonic calibration standards being used during the third 10-year interval ISi at Surry Power Station, Unit 1. The list should include the calibration standard identifications, material specifications, sizes, and any variance from Code requirements.
Response
See attached list of calibration standards.
E. NRC:
Relief Request No. 4: IWD-2500-1 requires a system hydrostatic test in accordance with IWD-5223, System Hydrostatic Test, for Class 3 pressure retaining piping.
The Licensee stated that the Component Cooling Water System is utilized for cooling important safety-related components associated with the nuclear core. In addition, the licensee states that portions of this system cannot be isolated, in most instances, without removing fuel totally from the core, and that this action would be time consuming and delay unnecessarily the refueling process. It appears that the required hydrostatic test could be done in conjunction with vessel inspections requiring total removal of the fuel. Please provide further justification for not performing the Code-required hydrostatic test.
Response
Since Code Case N-498-1, Alternative Rules for 10-Year System Hydrostatic Testing for Class 1, 2, and 3 Systems, was recently approved by ASME, the need for this relief request will probably not exist, when the third interval 10-year hydrostatic tests are required (approximately 1 O years from now). As such, Relief Request No. 4 is withdrawn. If at a later date the need for relief is again apparent (i.e., Code Case N-498-1 is not endorsed by the NRC), a separate relief request will be submitted identifying specific areas where impracticality exists for performance of hydrostatic tests in the component cooling water system along with the basis.
F. NRC:
Relief request No. 11: IWA-5242(a), states that for systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for visual examination VT-2.
The Licensee states that insulation will be removed and a direct visual inspection for evidence of leakage at pressure retaining-retaining bolting will be performed at the required frequency.
However, the system/component may or may not be at pressure.
During a conference call held March 11, 1994, the licensee agreed to a
~~
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four-hour pressure test hold time prior to performing the VT-2 visual examination. Please confirm that the required VT-2 visual examination will be performed at test pressure after a 4-hour hold time at the required test pressure.
Response
Applicable insulated pressure boundary bolting inspected as described in Relief Request No. 11 will receive a visual (VT-2) examination without removing the insulation following a 4-hour hold time at the required test pressure.
G. NRC:
Verify that there are no additionaL relief requests, other than those submitted July 16, 1993. If additional relief requests are required, the licensee should submit them for staff review.
Response
Separate correspondence has been submitted to utilize Code Cases N-416-1 (Serial No.94-320, dated June 22, 1994), and N-524 (Serial No.93-754, dated December 10, 1993) in the third interval. These code cases have not been approved by Regulatory Guide 1.147.
Additionally, the requirements of the first addenda to ASME/ANSI OM-1987, Part 4, are presently being reevaluated for visual examination of snubbers. It is anticipated that a relief request will be needed to clarify administrative differences between this standard and the guidance provided in Generic Letter 90-09, "Alternative Requirements For Snubber Visual Inspection Intervals and Corrective Actions", which was incorporated in Technical Specification 4.17.
SURRY NUCLEAR POWER PLANT UNIT #1 AND #2 CALIBRATION BLOCKS NOMINAL IDENTITY OR IDENTITY SIZE/SCH EDU LE HEAT NUMBER MATERIAL COMPONENT/SYSTEM PIPING BLOCKS VIR-1A 2.758"T x 12"L x 3"W 5160C-1 SA351 GR CF8A Reactor Coolant Pipe (from ELL Side)
VIR-2 30" 1.1 "T 3G5682 SA515 GR 70 CS 30" Mainsteam Piping VIR-3 14" SCH 140 1.25"T 2637-4-2 SA376 TP 316 SS 1 4" Feed water Piping VIR-4 14" SCH 80.750"T L45865 SA106 GR B CS 14" Feedwater Piping VIR-4A 14" SCH 80.750"T 48082 SA355 GR P22 14" Feedwater (80-Repl) Piping VIR-5 14" SCH 40.438"T 71771 SA358 TP 316 SS 1 4" SCH 40 Piping VIR-6 12" SCH 140 1.125"T F0959 SA312 TP 304 SS 12" SCH 140 Piping VIR-7 12" SCH 405.375"T 805222-1 SA312 TP 304 SS 12" SCH 405 Piping VIR-9 1 O" SCH 140 1.OO"T 061232 SA312 TP 304 SS 1 O" SCH 140 Piping VIR-10 1 O" SCH 120.844 "T 6-448 SA312 TP 304 SS Seal Water Injection Filter VIR-11 1 O" SCH 405.365 "T 1971-12-1-2 SA31 2 TP 31 6 SS 1 O" SCH 40S Piping VIR-14 6" SCH 160.719"T M2060 SA376 TP 304 SS 6" SCH 160 Piping VIR-15 6" SCH 120.562"T M9948 SA376 TP 316 SS 6" SCH 120 Piping VIR-16 6" SCH 80.432"T N14446 SA106 GR B CS 6" SCH 80 Piping VIR-17 31"1.5"T 3G8217 SA515 GR 70 SS 32" Mainsteam Piping VIR-18 4" SCH 160.531"T 01038 SA312 TP 304 SS CROM VIR-19 4" SCH 120.438"T M6108 SA376 TP 316 SS 4" SCH 1 20 Piping VIR-20 3" SCH 160.438"T N7212 SA376 TP 316 SS 3" SCH 1 60 Piping
NOMINAL IDENTITY OR IDENTITY SIZE/SCH EDU LE HEAT NUMBER MATERIAL COMPONENT/SYSTEM VIR-21 2" SCH 160.344"T 01003 SA376 TP 316 SS 2" SCH 160 Piping VIR-32 6" SCH 40S.280"T M9959 A312 TP 304 SS 6" SCH 40S Piping VIR-33 8" SCH 40S.322"T M0937 A31 2 TP 31 6 SS 8" SCH 40S Piping VIR-34 16" SCH 80.844"T L21488 SA106GRBCS 16" Feedwater Piping*
VIR-35 30" 1.810"T 678344 SA155 KC60 CL 1 CS 30" Tee Mainsteam Piping VIR-44 2.320"Tx27.5"1Dx32.14"0D J6954 A376 TP 304 N RC Loop Pipe Block VIR-45F 2.625"Tx31 "1Dx36.25"0D J6959 A376 TP 304 N RC Loop Pipe Block VESSEL BLOCKS VIR-8 12" SCH 20.250"T 8051726 SA312 TP 304 SS Seal Water Heat Exchanger VIR-13 8" SCH 120.719"T M0176 SA312 TP 304 SS Excess Letdown HT /Ex VIR-23 6.2"T x 6"W x 21.8"L B&W SA508 CL 2 RV-Closure Head-to-Flange Weld Piece 1 VIR-24 5.2"T x 6"W x 18.2"L B&W SA508 CL 2.
Channel Head to Tubesheet Piece 1 VIR-25 4.375"T x 6"W x 15.5"L D8366-5 SA533 GR A CL 1 Pressurizer VIR-26 3.5"T x 6"W x 18.2"L D8366-5 SA533 GR A CL 1 Steam Generator (Sec. Side)
VIR-29A
.627"T x 4"W x 9"L 42204 A240 TP 304 SS Non Regen. Heat Exchanger VIR-30
.313"T x 4"W x 9"L 30106 A240 TP 304 SS Volume Control Tank VIR-12 8" SCH 160.906"T 2626-8-1 SA312 TP 304 SS Regen Heat Exchanger
NOMINAL IDENTITY OR IDENTITY SIZE/SCHEDULE HEAT NUMBER MATERIAL COMPONENT /SYSTEM SIZING BLOCKS VP-. 25-CS-03
,25R 321-0676 A36 1 /4" Sizing Block CS VP-.50-CS-03
.50" 331-0889 A36 1/2" Sizing Block CS VP-.75-CS-03
.75" 1-57528 A36 3/4" Sizing Block CS VP-1.0-CS-03 1.00" 333-0889 A36 1.O" Sizing Block CS VP-1.25-CS-OJB 1.25" 85489 A36 1.25" Sizing Block CS 10%-50%
VP-1.25 CS-OJA 1.25" 85489 A36 1.25" Sizing Block CS 60%-90%
VP-1.50-CS-OJB 1.50" 60378 A36 1.50" Sizing Block CS 10%-50%
VP-1.50-CS-OJA 1.50" 60378 A36 1.50" Sizing Block CS 60%-90%
VP-1.75 CS-03B 1.75" 72674 A36
- 1. 75" Sizing Block CS 10%-50%
VP-1. 75-CS-OJA 1.75" 72674 A36
- 1. 75" Sizing Block CS 60%-90%
VP-2.0-CS-03B 2.00" 83427 A36 2.0" Sizing Block CS 10%-50% e VP-2.O-CS-03A 2.00" 83427 A36 2.0" Sizing Block CS 60%-90%
VP-.25-SS-03
.25" 130359 A479 TP 304 1 /4" Sizing Block SS VP-.50-SS-03
.50" 34214 A479 TP 304 1 /2" Sizing Block SS VP-. 75-SS-03
.75" 70777 A479 TP 304 3/4" Sizing Block SS VP-1.O-SS-03 1.00" 36463 A479 TP 304 1.O" Sizing Block SS VP-1.25-SS-OJB 1.25" 28498 A479 TP 304 1.25" Sizing Block SS 10%-50%
VP-1.25-SS-OJA 1.25" 28498 A479 TP 304 1.25" Sizing Block SS 60%-90%
VP-1.50-SS-OJB 1.50" A13072 A479 TP 304 1.50" Sizing Block SS 10%-50%
VP-1.50-SS-OJA 1.50" A13072 A479 TP 304 1.50" Sizing Block SS 60%-90%
VP-1. 75-SS-038 1.75" AH6895 A479 TP 304 1.75" Sizing Block SS 10%-50%
VP-1.75-SS-OJA 1.75" AH6895 A479 TP 304 1.75" Sizing Block SS 60%-90%
VP-2.50-SS-OJB 2.50" A14267 A479 TP 304 2.50" Sizing Block SS 10%-50% e VP-2.50-SS-OJA 2.50" A14267 A479 TP 304 2.50" Sizing Block SS 60%-90%
VP-3.0-SS-03B 3.00" A14394 A479 TP 304 3.0" Sizing Block SS 10%-50%
VP-3.0-SS-OJA 3.00" A14394 A479 TP 304 3.0" Sizing Block SS 60%-90%
IDENTITY VIR-36 VIR-37 VIR-38 VIR-39 VIR-40 VIR-41 NDE-LS-88 LSVN-04 RCP-03 RPV-03 NOTES:
NOTE 1:
NOTE 2:
NOTE 3:
NOMINAL SIZE/SCHEDULE 5.75" Dia. x 10.5"L 5.75" Dia. x 18"L 5.75" Dia. x 33"L 4.32" Dia. x 18.25"L 4.32" Dia. x 10.63"L 4.32" Dia. x 6.81 "L 2.62" Dia. x 22.5"L 3.0" Dia. x 22.5"L 4.5" Dia. x 30.5"L 6.0" Dia. x 63.25"L IDENTITY OR HEAT NUMBER MATERIAL BOLTING BLOCKS 112863 112863 112863 112863 112863 112863 60300 60300 X7225 SA540 GR 824 SA540 GR 824 SA540 GR 824 SA540 GR 824 SA540 GR 824 SA540 GR 824 A286 Carpenter A286 Carpenter SA540 GR 823 SA540 GR 824 COMPONENT/SYSTEM Reactor Vessel Stud 80W80 Reactor Vessel-Stud 80W80 Reactor Vessel-Stud 80W80 Reactor Coolant Pump Stud Reactor Coolant Pump Stud Reactor Coolant Pump Stud Loop Stop Valve Bolt Loop Stop Valve Stud Reactor Cool Pump Reactor Vessel Closure Head Stud Bolt Notches for piping < 1" and vessels s 1" thick are not staggered as specified by Figure 111-3230-1. Satisfactory ultrasonic system calibration can be performed with the existing calibration blocks.
Notches for piping calibration blocks < 1 % " thick are located 1 T from the end of block instead of a minimum of 1 % " as specified by Figure 111-3230-1. Satisfactory ultrasonic system calibration can be performed with the existing calibration blocks.
Blocks VIR-23, VIR-24 and VIR-25 are partially clad instead of fully clad as shown by Figure T-441.1. The portion of the calibration blocks which contains the calibration reflectors is clad. Satisfactory ultrasonic system calibration can be performed with the existing calibration blocks.
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e FIGURE 1-1. General Assembly and Final Machining