ML17056A807
| ML17056A807 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/26/1990 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML17056A805 | List: |
| References | |
| NUDOCS 9005030169 | |
| Download: ML17056A807 (44) | |
Text
ENCLOSURE 2
FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM EVALUATION OF REVISED AND BESUBHITED RELIEF REQUESTS NIAGARA MOHAWK POWER CORPORATION NINE NILE POINT NUCLEAR STATION, UNIT 1 DOCKET NO. 50-220 I.
BACKGROUND INFORMATION 10 CFR 50.55a(g) requires examinations and tests of nuclear power facilities piping and components to be performed in accordance with the requirements of the applicable edition and addenda of Section XI of the ASthE Code.
If it is impractical to meet the requirements, the licensee of the facility is required to notify the Commission and submit information in support of the determination that the requirements are impractical to perform.
The Commission evaluates the determination that the requirements are impractical and may grant relief or impose alternative requirements.
By letters dated April 1, 1987, March 15, September 30 and December 23, 1988, February 24, April 12, May 15, July 25, August 8, August 16, September 8,
and November 9, 1989, Niagara Mohawk Power Corporation transmitted to the NRC the First Ten-Year Interval Inservice Inspection Program relief requests, additional information, revised and withdrawn relief requests and relief requests that were resubmitted after additional information was obtained.
The NRC transmitted an SEB/TER to Niagara mohawk Power Corporation by letter dated August 11,, 1989, in which relief requests, revisions, and additional information were evaluated for the submittals transmitted to the NRC From April 1, 1987 through August 8, 1989.
Relief Requests lIIRR8A, Revision 1, 1IIRR
, Revision 5, lIIRR10, Revision 3 and 1IIRR7, Revision 2 transmitted to the NRC by letters dated September 8 and November 9, 1989, are evaluated herein pursuant to 10 CFB 50.55a(g)(6)(i) to determine if the necessary findings can be made to grant relief as requested.
II.
SUPPORTING INFORMATION, EVALUATION, AND CONCLUSIONS A.
Relief Request Number 1IIRR8A, Revision 1, (11/9/89 Ltr, TAC No. 75317) 1.
COMPONENT IDENTIFICATION System:
Duality Group:
Component
Description:
Pressure Retaining Melds in Feedwater Heat Exchangers
--vovvozoib< <ggOO220 q yg)Vedb pgR PQOC pDC
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3.
ASME CODE SECTION XI FIRST INTERVAL INSPECTION REQUIREMENTS 1974 Edition with Addenda through Summer 1975.
Class 2, Category C-A, Item C1.10 requires volumetric examination.
RELIEF REQUESTED Relief is requested from 100% volumetric examination of vessel circumferential welds at structural discontinuities of one of similar pressure vessels in multiple loops.
Relief is requested for two (2) of the required vessel welds.
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BASIS FOR RELIEF 5.
Welds HX-30-06-DOME and HX-51-12-DOME were not inspected due to limitations of design and geometry.
Access to perform in-place vessel ultrasonic examinations was not provided for in the original design.
The geometry of the weld joint (i.e. shell curvature and weld end preparation) has a limiting effect on examination coverage.
ALTERNATE EXAMINATION 6.
7.
Radiography as an alternate method is not practical to perform due to the same design and geometric conditions which limit ultrasonic examination.
Any examination additional to the examination performed would result in an undue burden without a compensating increase in assurance of vessel weld integrity or plant safety.
PLANT QUALITY AND SAFETY The completed, required functional, hydrostatic and other pressure tests (as applicable) provide an acceptable level of assurance of vessel weld integrity.
RADIATION CONSIDERATIONS Radiation considerations are not a basis for this request for relief.
8.
STAFF EVALUATION AND CONCLUSIONS The Code requires the Feedwater Heat Exchanger Dome-to-Tube Sheet welds to be examined volumetrically 100%.
The accessibility of the welds for 100% volumetric examination is limited by tube plates, lifting lugs, support saddles, and nozzles.
Compliance with the Code requirement would require redesiqn of the heat exchanger.
However, the licensee has indicated that one weld can
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E be examined 80% axially and 99% circumferentially and the other 32% axially and 99% circumferentially.
The examinations of the high percentages of the weld volumes will provide adequate assurance that, if flaws exist, they will be detected.
The staff therefore, concludes that relief from performing 100%
volumetric examination of the welds may be granted as requested.
B.
RELIEF REQUEST NUMBER 1IIRR9, Revision 5
(11/9/89 Ltr, TAC NO. 75317) 1.
COMPONENT IDENTIFICATION System:
Various Quality Group:
B Component
Description:
Pressure Retaining Welds in Piping 2.'SNE CODE SECTION XI FIRST INTERVAL INSPECTION REQUIREMENTS 1980 Edition with Addenda through Winter 1981 Class 2, Category C-F, Item Number C5.11, C5.31 require a
surface examination, Item Number C5.21 requires a volumetric and surface examination.
3.
RELIEF REQUESTED Relief is requested for 100% surface and/or volumtric examination of the area/volume delineated in Figure IWC-2500-7 and IWC-2500-9.
Relief is requested for the three (3) piping welds listed below:
81-SW-778 02-FW-11 80-SW-08A-A 4.
BASIS FOR RELIEF The welds listed were not fully inspected by ultrasonic and/or surface methods due to limitations of design,
- geometry, and material of construction.
Fitting configuration limits meaningful examination of one (1) weld.
Saddles over branch connections retrict access to one (1) weld.
Integrally attached obstructions limit access to one (1) weld.
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ALTERNATE EXAMINATION Acceptable ASNE Section XI examinations were performed on the saddle welds obstructing 80-SW-08A-A Radiography of fitting welds would not result in a meaningful examination for detection of service generated flaws.
Radiographic or surface examination in addition to examinations performed would result in an undue burden without a compensating increase in assurance of piping weld integrity or plant safety.
6.
PLANT QUALITY AHD SAFETY The examinations as performed, together with the completed system pressure tests (as applicable),
provide an acceptable level of assurance of piping weld integrity.
7.
RADIATION CONS IDERATIOHS Radiation considerations are not a basis for this request for relief.
8.
STAFF EVALUATION AND CONCLUSIONS The three welds for which the licensee has requested relief from Section XI examination requirements cannot be examined in accordance with those requirements because they are either obstructed by attachments, covered by a piping fitting, or have geometry that prevents the examination method from attaining full coveraqe of the welds.
The licensee indicated that weld 81-SW-77B was examined by surface method with coverage of 78%.
Weld 02-FW-11 was examined volumetrically, axial and circumferential coverage eoual to 92% and 78K respectively.
Weld 80-SW-08A-A is completely covered by saddle welds on which the licensee performed surface examinations as an alternative.
Compliance with Code requirements would necessitate modifications to remove integrally attached obstructions, redesign to employ different fittings and redesign to replace branch connections with a more examinable configuration.
The staff has determined that the examination requirements of Section XI are impractical to perform on welds 81-SW-77B, 02-FW-11, and 80-SW-08A-A and that the partial and alternative exmainations performed provide assurance of the structural integrity of the welds.
We conclude that relief from performing the full Code requirements may be granted as requested.
C.
RELIEF REQUEST NUMBER lIIRR10, REVISION 3 (9/8/89 LTR, TAC No. 74852) 1.
COMPONENT IDENTIFICATION System:
Core Spray and Containment Spray Quality Group:
8 Component
Description:
Pressure Retaining Welds in Pumps 2.
ASME CODE SECTION XI FIRST INTERVAL INSPECTION REQUIREMENTS 1974 Edition with Addenda through Summer 1975; and the 1980 Edition through Winter 1981 Addenda.
Class 2, Category C-G, Item Number C6.10 requires volumetric examination.
3.
BELIEF REQUESTED
'a ~
Relief is requested from volumetric examination of pump casing welds in one of the streams of the piping system in the first inspection interval.
Relief is requested for all of the required pump welds, and, b.
Relief is also requested from performing surface examination of inaccessible pump casing welds listed below:
80-PM-03-SH-7A 80-PM-03-SW-8 80-PM-03-SW-8A 80-PM-03-SH-9 80-PM-03-SH-11 80-PM-03-SH-12 81-PM-24-SW-7A 4.
BASIS FOR RELIEF 81-PM-24-SW-8 81-PM-24-SH-8A 81-PM-24-SW-9 81-PM-24-SW-11 81-PM-24-SH-12 81-PM-24-SH-5 a.
The pressure retaining pump casing welds were not ultrasonically inspected due to limitations of design and geometry.
Due to fillet weld joints or right angle surfaces of the nozzles, top column, internal flanges and outer casing, ultrasonic examination of accessible weld would not result in meaningful examination data.
Relief
, is requested for casing welds in one of each of the core spray multi-stage vertical and containment spray pumps.
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t Radiography as an alternate examination of pump casing welds would not result in a meaningful examination.
The differing surface curvatures at right angles to each other would necessitate multiple exposures at multiple locations, compounding evaluation of results.
Additional radiographic examination would result in an undue burden without a compensating increase in assurance of pump casing weld integrity or plant safety.
b.
In 1984 the program plan was updated to the 1980 Edition, Winter 1981 Addenda of Section XI.
This edition requires surface examination of the pump casing welds.
Six welds on each pump are inaccessible for surface examination from the pump exterior.
These welds:
80-PH-03-SM-8, 80-PH-03-SM-9, 80-PH-03-SM-11, 81-PH-24-SW-8, 81-PH-24-SW-9 and 81-PH--24-SM-11 are located on the lower section of the pump housing and are encased in concrete.
80-PH-03-SW-12, 81-PH-24-SW-12, 80-PH-03-SM-7A, 81-PH-24-SM-7A, 80-PH-03-SW-8A, and 81-PH-24-SW-8A are inaccessible due to pump configuration.
Partial coverage was attainable for one additional weld.
The Meld Required Area achieved for 81-PH-24-SW-5 was 88%.
It was partially obstructed by instrument lines.
5.
ALTERNATE ENAHINATION Surface examinations of the accessible welds has been performed in accordance with the Winter 1981 Code requirements.
In addition, a visual inspection of the pump internals is conducted when the pump is disassembled for maintenance.
6.
PLANT QUALITY AND SAFETY The examinations as performed, together with the required hydrostatic and pressure test provide an acceptable level of assurance of pump casing weld integrity.
7.
RADIATION CONSIDERATIONS Radiation considerations are not a basis for this request for relief.
8.
STAFF EVALUATION AND CONCLUSIONS The examinations requirements for the welds listed are those of the 1980 Edition, Minter 1981 Addenda.
The Code requires a
surface examination of 100% of the pump casing welds to be performed on one pump in multiple pumps of similar design, size, function and service in a system.
The welds cited in the licensee's request cannot be examined in accordance with the requirements because they are inaccessible, either buried in concrete or in areas of the casing where the geometry prevents access.
Compliance with Code requirements would require extensive modifications to expose the welds or redesign of the subject pumps.
The licensee performed surface examinations on
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accessible welds, covering 88% of weld 81-PM-24-SW-5.
The staff finds the requirements impractical for the welds listed and has determined that the alternative examinations proposed by the licensee will provide assurance of the pump casings'ontinued structural integrity.
Me conclude that relief from the examination requirements may be granted as requested.
D.
RELIEF REQUEST NUMBER 1I IRR7, REVISION 2 (9/8/89 Ltr, TAC NO 74852)
COMPONENT IDENTIFICATION System:
Quality Group:
Component
Description:
Various A
Pressure Retaining Welds in Piping 2.
ASME CODE SECTION XI FIRST INTERVAL INSPECTION REQUIREMENTS 1980 Edition with Addenda through Winter 1981.
Class 1, Category B-J, Item B9.10, B9.30 require a surface and a volumetric examination.
3.
RELIEF REQUESTED Relief is reouested from the requirement to examine, by the volumetric and surface
- methods, piping welds in the reactor coolant pressure boundary.
Relief is. requested for the four (4) welds listed below:
01-FW-06 Ol-SW-16X 01-SW-2A 31-SW-27A 4.
BASIS FOR RELIEF Three (3) of the welds listed were not fully inspected volumetrically due to limitations of design,
- geometry, and material of construction.
The dendritic structure of those welds which are made of stainless steel material can result in both sound redirection and attenuation phenomena which limit ultrasonic interrogation.
- Thus, such welds necessitate examination from both sides in order to be fully examined.
In general both the geometry of non-parallel surfaces and the product form of the material preclude meaningful ultrasonic examination.
One (1) weld was not fully examined due to permanent hanger interference.
The percentage of Weld Required Volume/Area (WRV/HRA) that was completely examined is tabulated with the nature of obstruction in the licensee's submittal.
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ALTERNATE EXAMINATION No alternate examinations were performed.
The required surface examination was performed on all welds to the extent practical.
Radiography would not yield results with meaningful evaluation for service generated defects.
Volumetric or surface examination additional to examinations performed would result in an undue burden without a compensating increase in assurance of piping weld integrity or plant safety.
6.
PLANT QUALITY AND SAFETY The examinations as performed, together with the completed, required
- leakage, hydrostatic and other pressure tests (as applicable),
provide an acceptable level of assurance of piping weld integrity.
7.
RADIATION CONSIDERATIONS Radiation considerations are not a basis for this request for relief.
8.
STAFF EVALUATION AND CONCLUSIONS Three of the welds (01-FW-06, 01-SW-16, 01-SW-2A) for which the licensee has requested relief from the examination requirements are welds made at weldolet-to-valve or weldolet-to-pipe junctions.
Weld 31-SW-27A joins an elbow to a pipe.
The geometry of the weldolets-to-valve or pipe prevents coverage of the weld volume required to be examined.
The elbow-to-pipe weld was prevented from being fully examined by the location of a permanent hanger.
This weld was volumetrically examined over 79% of the required volume and examined by surface method over 85% of the required area.
The licensee indicates that all four welds were examined by surface method.
Compliance with Code requirements would necessitate redesign of the piping and modification or redesign of the hanger.
The staff has determined that the geometry of the weldolets and the permanent hanger make the Code examination requirements impractical to be fully implemented.
The limited examinations performed and other tests (pressure and visual) will provide assurance that any significant flaws will be detected.
The staff therefore concludes that relief from the Code Requirements may be granted as requested.
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III. CONCLUSION Based on the review summarized herein the staff has determined that pursuant to 10 CFR 50.55a(g)(6)(i) granting relief where the inspection requirements are impractical is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest considering the burden that could result if the requirements were imposed on the fac i lity.
Date:
Princi al Contributor:
George Johnson
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TABLE 1 Nine Mile Point Nuclear Station, Unit 1 Page 1 of 13
SUMMARY
OF RELIEF RE UESTS Relief Request Exam.
Number Cat.
Item No.
System or
~Com onent Volume or Area to be Examined Required Method Licensee Proposed Belief Requ Alternative Status
- 1IIRR1, Bev.
2 B-D B1.4 Reactor Pressure Vessel RV1-565B RV1-565D RV1-568-25 RV2-566B RV2-567B RV3-565B RV3-565D RV4-566A RV4-566C RV6-566A RV6-567 Nozzle-to-vessel welds:
RV3-566A RV3-566C Nozzle to vessel welds Volumetric and nozzle inside radius sections:
RV1-565A BVl-565C RV1-565E RV2-566A RV2-567A RV3-565A BV3-565C RV3-565E RV4-566B RV4-566D RV6-566B None.
Ultrasonic examination to extent practical and ID surface examination of nozzles RV4-566(A, B, C, and D) and RV6-567 Granted
- 1IIRR2, B-0 Rev.
1 B1.18 Control Rod Drive Housings Welds:
BV-CRD-Rl RV-CRD-S1 RV-CRD-T3 BV-CRD-U2 Volumetri c examination of 10% of peripheral control rod drive housings Volumetric examination to maximum extent practical and volumetric examination of 50% of four additional welds to meet intent of code Granted
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Nine Mile Point Nuclear Station, Unit 1 Page 2 of 13 TABLE 1
SUMMARY
OF RELIEF REQUESTS Relief Request Number 1IIRR17 Rev.
1 5/15/89 Exam.
Cat.
B-H Item No.
B1.12 System or
~Con onent Reactor Pressure Vessel Volume or Area to be Examined Skirt integral attach-ment weld Required Method Volumetri c examination of at least 10% of weld length Licensee Proposed Alternative Surface examination the outer surface per 80W81 Relief Bequest Status GrantedO of E-2, B-B Rev.
1 Bl.2 Reactor Pressure Vessel Circumferential and longitudinal shell welds Volumetri c None.
Volumetri c examination to maximum extent practical Granted E-4.
Rev.
1 B-G-1 B1.8 Reactor Pressure Vessel Closure studs and nuts Surface Magnetic particle surface examination of accessible portions of the closure studs and nuts; ultrasonic examination of the threaded sections of the nuts Granted 1 IIRR18, B-G-1 Rev.
0 8/16/89 B6.220 Shutdown Cooling Flange surfaces of Check Valve 38-12 Visual VT-1 None Denied
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Nine Mile Point Nuclear Station, Unit 1 Page 3 of 13 TABLE 1
SUMMARY
OF RELIEF BEQUESTS Relief Bequest Number Exam.
Cat.
Item No.
System or
~Con onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Bequest Status 1IIRR19 Rev.
0 9/8/89 8-H-1 812.40 Hain Steam Valve Body Weld 87-06130-SW-1 Volumetri c Volumetri c Examination to maximum extent practical, approx.
80%
Granted 1IIRB6 8-F 1 IIBB7, 8-J Rev.
2 9/8/89 85.130 89.10 89.11 Reactor Mater Clean-Up Piping Hain Steam Feedwater Elbow-to-pipe weld 33-FH-RCU-10-2A Circumferential and Branch Pipe Connection welds:
01-FW-06 01-SW-2A 01-SH-16X-31-SH-27A Volumetri c and surface Volumetric and surface None Volumetric and surface to extent practical Denied Granted
- 1IIRRll, 8-J Rev.
5 11/9/89 89.11 and 89.12 RPV Head Spray and
- Vent, Shutdown
- Cooling, and Core Spray System Piping Volume tri c and surface Nonconforming service sensitive piping welds (NUREG-0313):
P-34-SW-02 P-NES-37-51 38-FH-4-D 40-FH-16 40-FH-16-D 40-FW-30 40-FH-55 40-FH-30-D 40-FW-34A None Volumetric and surface exam to maximum extent practical Granted*
(continued on page 4)
- Based on evaluation of 1IIBR11, Revision 2 in SEB/TEB transmitted to Licensee by letter dated 8/11/89
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Nine Ni 1 e Point Nuclear Stati on, Unit 1
Page 4 of 13 TABLE 1
SUMMARY
OF RELIEF BEOUESTS Rel ief Request Number Exam.
Cat.
Item No.
System or
~Com onent Volume or Area to be Examined Required Nethod Licensee Proposed Alternative Relief Request Status (cont'd) 8-J
- 1IIRR11, Rev.
5 11/9/89 89.11 and 89.12 RPV Head Spray and
- Vent, Shutdown
- Cooling, and core 40-SM-37A 40-SM-46A 39-09R-SW-1 39-SW-34A 38-SM-27A 33-FM-BCU-10-2A 33-FM-BCU-10-28 33-FW-BCU-8-38 40-S'W-37A-U 40-SW-46A-U 39-10B-SM-1 38-SM-3A 33-FW-RCU-9-2A Volumetri c and surface to maximum extent practical None Volumetric and surface Granted 89.21 RPV Head Spray and Vent Piping Nonconforming servi ce Surface sensitive piping (NUREG-0313) weld P-34-FW-17 None Granted
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Nine Mile Point Nuclear Station, Unit 1 Page 5 of 13 TABLE 1
SUMMARY
OF BELIEF REQUESTS Relief Request Number PSIBB1 Exam.
tat.
8-F Item No.
85.130 89.11 System or
~con onent Reactor Water Cleanup Piping Emergency Cooling and Reactor Mater Cleanup Piping Volume or Area to be Examined Replacement Weld 33-FW-0261-04 Replacement welds:
39-FM-4043-016 39-FW-4043-017 39-FM-4043-030 39-FM-4043-031 33-FW-0261-01 33-FW-0261-02 33-FM-0261-06 Required Method Volumetri c and surface as required by Paragraph IWB-2200(c)
Volumetric and surface as required by Paragraph IWB-2200(c) licensee Proposed Alternative Volumetric and surface examinations to maximum extent practical Volumetri c examination to maximum extent practical and Code-required surface examination Relief Request Status Granted
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Granted PS IRB2 8-J 89.11 Reactor Recirc.
Piping Melds altered by Induction Heating for Stress Improvement (25 welds)
Volumetri c and surface as required by paragraph IMB-220(c)
None.
Volumetri c examination only (limited volumetri c examination of welds 32-FW-12S-F 32-FM-13S-5 32-FW-13D-6 32-F W-14D-6 32-FW-15D-3 32-FW-15S-4)
Denied for surface examination Granted for partial volume$ric exam>nation of the six welds listed
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Nine Nile Point Nuclear Station, Unit 1 Page 6 of 13 TABLE 1 SUNNARY OF RELIEF RE UESTS Relief Request Number Exam.
Cet.
Item No.
System or
~Con onent Volume or Area to be Examined Required Nethod Licensee Proposed Alternative Relief Request Status
- 1PSIRR3, 8-J Rev.
0 11/09/89 89.11 Emergency Cooling Valve-to-Reducer Weld 39/32-FW-11S-24 Volumetri c and surface Surface and zero degree ultrasoni c Granted 1I IRR3, Rev.
2 8-L-2 85.6 Reactor Recirc.
Pumps Casing Welds Withdrawn by Licensee in 12/23/88 submittal
- 1IIRR4A, 8-N-2 86.7 Rev.
1
- llIRR48, 8-N-2 86.7 Rev. I Valve Bodies Valve Bodies Inter nal surfaces Internal surfaces Withdrawn by Licensee in 9/30/88 submittal Mithdrawn by Licensee in 9/30/88 submittal 1I IRR5, 8-K-1 810.30 Va1 ves Rev.
3 9/8/89 Integrally weld attachments:
01-03-SW-1 Ol-04-SM-1 33-03-SW-1 33-04-SW-1 38-02-SH-1 31-H-6 ed Volumetri c or surface 38-12-SW-1 40-02-SW-1 40-12-SW-1 42.1-03-SW-l 301-112-SW-1 None. Surface Granted*
examination to maximum extent practical
- Based on evaluation of 1IIRP5, Rev.
2 in SER/TER transmitted to Licensee by letter dated 8/11/89.
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Nine Mile Point Nuclear Station, Unit 1 Page 7 of 13 TABLE 1
SUMMARY
OF RELIEF RE UESTS Relief Request Number Exam.
cet.'tem No.
System or
~corn onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Bequest Status 1IIRR8A C-A C1.1 Feedwater Circumferential Welds Volumetric Heat Fxchanger HX-30-06-Dome and HX-51-12-Dome None Withdra 5/15/89 llIBR8B C-B C1.2 Feedwater Heat Exchanger Nozzle-to-vessel we 1ds:
Volumetri c HX-30-06-IN HX-30-06-ON HX-51-12-IN HX-51-12-ON None.
Base-line magnetic particle examinations were performed Granted
- 1IIRB9, C-F Rev.
5 11/09/89 C5.11 Core Spray Pipe-to-elbow weld: 81-SH-77B Surface None. Surface examination to maximum extent practical Granted C-F C5.21 Feedwater Piping C ircumferenti a 1 weld: 02-FW-11 Volumetri c and surface None.
Volumetric examination of accessible portions and Code-required surface examination C-F C5.31 Core Spray Branch Connection Weld: 80-SH-08A-A Surface None Granted
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Nine Hile Point Nuclear Station, Unit 1 Page 8 of 13 TABLE 1 SUHHABY OF RELIEF BEQUESTS Relief Request Number Exam.
Cat.
Item No.
System or
~Com onent Volume or Area to be Examined Required Hethod Licensee Proposed Alternative Belief Bequest Status 1IIRR12 Rev.
1 5/15/89 C-F C5.21 and C5.22 Shutdown Cooling and Emergency Cooling Piping Nonconforming service sensitive piping welds (NUREG-0313):
38-SM-100-U
'8-SW-102 38-SM-25A 38-SW-84 39-FM-15 39-FM-40 39-FW-7 Volumetri c and surface None.
Volumetric and surface examinations to maximum extent practi cal Withdr 5/19/89
- 1IIBR10, C-F Rev.
2 5/15/89 1IIRB10 C-G Rev.
3 9/8/89 C3.1 C6.10 Core Spray and Containment Spray Pumps Core Spray and Containment Spray Pumps All pump casing-welds Pump casing welds:
80-PH-03-SM-7A 80-PH-03-SW-8 80-PH-03-SW-8A 80-PH-03-SW-9 80-PH-03-SM-11 80-PH-03-SW-12 81-PH-24-SM-7A 81-PN-24-SW-8 81-PH-24-SW-8A Volumetric (74S75)
Surface (80W81)
Surface examination per 80W81; visual of internal surface if disassembled None Relief not required Granted (Continued on Paoe 9)
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Nine Mile Point Nuclear Station, Unit 1 Page 9 of 13 TABLE 1
SUMMARY
OF RELIEF RE UESTS Relief Request Number Exam.
Cat.
Item No.
System or
~Com onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Belief Request Status (cont'd)
C-G lIIRR10 Rev.
3 9/08/89 C6.10 Core spray and contain-ment spray pumps Pump Casing Melds:
81-PN-24-SM-9 81-PN-24-SM-11 81-PM-24-SM-12 81-PN-24-SW-5 Surface (80M81)
Surface None Surface to extent possible Grante Granted lIIRR20
- 1IIRR15, Pev.
2 Reactor Recirculation System Class 1
1-inch nominal pipe size instrument lines Main Steam piping from the outboard isolation valves to the turbine stop valves Visual (VT-2) examination during system hydrostatic pressure test Hydrostatic test Visual (VT-2) examination during system leakage test Granted Withdr~
by LiceMee on 12/23/88
- lIIBR16, Rev.
1 Control Rod Drive Class 2 piping:
portion of the insert and withdraw lines inboard to the RPV from valves 101 (CBD-E) and 102 (CRD-F)
Hydrostatic test at pressure of 2188 psig per IWC-5220(a)
Hydrostatic test at pressure of 1145 psig in conjunction with Class 1
RPV and Class 2
CBD hydro-static test Granted
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Nine Nile Point Nuclear Station, Unit 1 Page 10 of 13 TABLE 1
SUMMARY
OF RELIEF RE UESTS Relief Request Exam.
Item System or Volume or Area Number Cat.
No.
~tom onent to be Examined Required Method Licensee Proposed Alternative Relief Request Status 1IIBB22 (5/15/89)
Reactor Class 1 one-inch Recirculation instrument line System Visual exam during hydro test VT-2 During system leakage test 1IIRR22, Bev.O withdrawn 9/8/89 duplicate of lIIRR20 1IIRR22 B-M-2 B12.50 Rev.
1 8/16/89 Emergency Condenser Feedwater Reactor Water Cleanup Valve Internal surfaces:
39-03, 39-04 31-07, 31-08 33-01 33-02 33-04 Visual VT-3 None Denied B-N-2 B12.50 Shutdown cooling Internal surf aces of valves:
38-01 38-02 33-13 Visual VT-3 None Denied
- 1IIRR25, Bev.
0 Core Spray 40-01, 09, 10, 11 40-02, 12 40-05, 06 Class 2 Reactor Core Spray System piping:
Motor Cooler for Core Spray Pump fill, from the first union to the inlet and outlet of the cooler: Motor Cooler for 'Core Spray Pump 8112, from the first union to the inlet and outlet of the cooler; Motor Cooler for Core Spray Pump 8121, from the first union (Cnntinn~d nn Pane 11 1 Visual VT-3 Hydrostatic test at pressure of 390 psig per IWC-5220(a)
None Inserv ice test performed at restart of the plant plant after 1988 refueling outage Denied Granted
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Nine Mile Point Nuclear Station, Unit 1 Page 11 of 13 TABLE 1
SUMMARY
OF RELIEF BEgUESTS C
C Belief Request Number (cont'dl
- 1IIRR25, Bev.
0 1I IBB14, Rev.
1 11IRR21 Exam.
Cat.
Item No.
System or Volume or Area
~Com onent to be Examined to the inlet and outlet of the cooler; Motor Cooler for Core Spray Pump 8122, from the first union to the inlet and outlet of the cooler; Bearing Coolers for Core Spray Topping Pump 8111, from the first union at PCV 81-57 to valves CS-C-2 and CS-C-3; Bearing Coolers for Core Spray Topping Pump 8112, from the first union at PCV 81-58 to valves CS-C-2 and CS-C-3; Bearing Coolers for Core Spray Topping Pump 8121, from the first union at PCV 81-59 to valves CS-C-2 and CS-C-3; and Bearing Coolers for Core Spray Topping Pump 8122, from the first union at PCV 81-60 to valves CS-C-2 and CS-C-3 Fuel Pool Cooling System Class 3
Piping Class 3 piping in the Nitrogen Purge system:
three portions of ASME Class piping from the Nitrogen Storage Tank 201.9-01 to their respective isolation valves, and six portions of ASME Class 3 piping from Nitrogen Storage Tank 12 to their respective isolation valves Required Method Hydrostatic test at pressure of of 390 psig per INC-5220(2)
Hydrostatic test Pneumatic 3 test at pressure of at least 1.10 times system design pressure Licensee Proposed Alternative Inservice Test Performed at restart of the plant after 1988 refueling outage Functional pressure test Relief Request Status Grante Mithdra by Licensee in 9/30/88 submittal Granted I
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Nine Mile Point Nuclear Station, Unit 1 Page 12 of 13 TABLE 1
SUMMARY
OF RELIEF RE UESTS Relief Request Number Exam.
Cat.
Item iio.
System or Volume or Area
~Com onent to be Examined Required Method Licensee Proposed Alternative Relief Request Status
- 1IIRR24, Rev.
0 Class 3 Control Rod Drive piping:
Bearing and Gear Oil Coolers for CRD Pump 011, from the first union at relief valve PSV 301-16A to valves CRD-73A and CRD-75B; and Bearing and Gear Oil Coolers for CRD Pump 812, from the first union at relief valve PSV 301-16B to valves CRD-74A and CRD-76B Hydrostatic test at pressure of 165 psig per IblD-5000 Inservice test of CRD system at restart of the plant after 1988 refueling outage Grante
- 1IIRR13, Rev.
1 Nonisolatable portions of Class 2 and Class 3 piping systems Hydrostatic test Mithdrawn by Licensee in 9/30/88 submittal 1IIRR26 C-C Rev.
1 9/8/89 C3.20 Core Spray C3.30 Feedwater Integral Attachment welds on pipe support anchor 81-A-4, 81-A-3 Pump supports:
29-01-SPRT-1 29-01-SPRT-2 29-02-SPRT-1 29-02-SPRT-2 29-03-SPRT-1 29-03-SPRT-2 100%, surface examination Partial surface Granted*
- Based on evaluation of 1IIRR26 in SER/TER transmitted to licensee by letter dated 8/11/89
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Nine Mile Point Nuclear Station, Unit 1 Page 13 of 13 TABLE 1
SUMMARY
OF RELIEF REQUESTS Relief Request Exam.
Item System or Number Cat.
No.
~Com onent Volume or Area to be Examined Required Method Licensee Proposed Relief Request Alternative Status 1IIRR27 Containment Spray System Motor Cooler for Containment Spray
- Pumps, 8112, II'121, 8122 Hydrostatic Pressure Test Test at lower Granted pressure
- lIIRR28, F-B Rev.
0 9/08/89 F2.10 F2.20 F2.30 F2.40 Feedwater Supports:
51-A-1 51-H-10 51-H-5 51-H-17 51-H-7 51-H-23 Visual None Granted
- 1IIRR29, B-A Rev.
0 9/08/89 lIIRR30 B-D Rev.
0 9/08/89 B1.40 Reactor Vessel B3.10 Reactor B3.20 Vessel Closure head flange welds Volumetric and surface Closure head-to-safety Volumetri c valve nozzle welds and inner radii CH-1-576 A-W thru CH-1-576-H-W CH-1-576 J-W thru CH-1-576-M-W CH-3-576 A-W thru CH-3-576-F-W CH-5-576 W
100% surface Granted volumetric to extent practical Volumetric Granted to extent practical
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