ML19257A550
| ML19257A550 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/04/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19257A546 | List: |
| References | |
| NUDOCS 8001040610 | |
| Download: ML19257A550 (36) | |
Text
.
E(pa arouq[0, UNITED STATES NUCLEAR REGULATORY COMMISSION Te(3 g
. n.
g, j/
\\7+.ciw
..+
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0. 22 TO FACILITY OPERATING LICENSE NO. OPR-66 DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANI A POWER COMPANY BEAVER VALLEY POWER STATION, UNIT NO.]
DOCKET NO. 50-334 As required by 10 CFR 50.55a(g), Duquesne Light Company has updated the Inservice Inspection and Testing Program for the Beaver Valley Unit 1 facility to the requirements of the 1974 Edition through summer 1975 Addenda of Section XI ASME Boiler and Pressure Vessel Code. Based on the infomation submitted by letters dated October 28, 1976, October 10, 1977, June 12,1978, July 24,1978 and August 10, 1979 and our review of this infomation, it has been detemined that certain requirements of the Code cannot be implemented because of component or system design, geometry, or materials of construction of the facility. Requested relief from those requirements have been evaluated and our deteminations to grant or deny the requests are documented below. These examination reliefs and required alternatives are summarized in Table 1 of the Safety Evaluation Report.
I.
INSERVICE INSPECTION A.
Class 1 Components 1.
Request relief from examination of the Lower Head ' ling to Peel Segment Circumferential Weld, Lower Head Peel Segment Meridional Welds, Lower Head Peel Segment to Disc Circum-ferential Weld, Closure Head Peel Segment to Disc Circum-ferential Weld.
(Item Bl.2, Examinaticn Category B-B.)
Code Requirement Volumetric examination of the shell longitudinal and cir-cumferential welds. Examination shall cover at least 10%
1687 302
. of the length of each longitudinal weld and 5% of the length of each circumferential weld during the inspection interval.
Examinations may be performed at or near the end of the inspection interval.
Licensee Basis Ter Requesting Relief The examination of the welds in the bottom head is restricted from inside the vessel by the locations of the adjacent incore instrumentation penetration. Examinations of those areas accessible between the penetrations and conduits will be per-formed from the outside surface to the extent practical as allowed by radiation levels. The closure head peel segment to disc weld is completely enclosed within the pattern of CRDM penetrations inside the shroud and is not accessible for examination as required by IWB-2600.
The general area radiation levels are expected to be 100 to 200 mr/hr and 400 to 500 mr/hr contact on the vessel shell. Examinations will not be performed if the examiner must receive a whole body dose in excess of 1250 mr in order to complete any one examination.
Evaluation The design of the lower and closure heads of the reactor vessel prevents examination, to the extent required by the Code, of the welds for which relief is requested. The licensee has stated that examination of those accessible areas between the incore instrumentation penetrations and conduits will be performed to the extent practical provided radiation levels permit such examinations. As an alternate examination of the lower head welds, the licensee has proposed to examine 60%
of one meridional weld and 5% of the adjacent portions of each circumferential weld. The staff has deterinined that the alternate examination proposed by the licensee and a visual examination of the welds during pressure tests will provide an acceptable level of safety and assurance of the structural integrity of these welds. We conclude that relief from the Code requirement may be granted for this examination.
1687 303
2.
Request relief from volumetric examination of the inner nozzle-to-vessel radiused section on the steam generator and pressurizer nozzles.
(Items B2.2 and B3.2, Examination CategoryB-D)
Code Requirement The extent of examination of each nozzle shall cover 100%
of the volume to be inspected as shown in Figure IWB-25000.
All nozzles shall be examined during each inspection interval.
Licensee Basis for Requesting Relief The steam generator and pressurizer nozzles are integrally cast with the vessel heads and therefore contain no nozzle-to-vessel welds. Due to the rough as-cast surface, geometric configuration, and radiation levels in the area, volumetric examination results will be limited.
Evaluation The licensee has agreed to attempt to exanine the nozzle-to-vessel radiused sections in accordance with the Code requirements. However, the design and materials of construction are expected to limit the results of the examinations. Because of the integrally cast fabrication of these components, it is the staff's ;;dgment that the areas required to be examined are not likely to be suscep-tible to inservice flaw initiation and that a visual examination of the radiused sections will provide adequate assurance of the structural integrity of these components.
We, therefore, conclude that relief from the Code require-ment may be granted provided a visual examination is performed.
3.
Request relief from 100% volumetric examination of steam generator nozzle safe-end-to-pipe welds from the nozzle side.
(Item B4.1, Examination Category B-F)
Code Requirement Volumetric and surface examination of all safe-ends during each inspection interval.
1687 504
a Licensee Basis for Requesting Relief The arrangements and details of the piping systems and components are such that some examinations as required by IWB-2600 are limited due to geometric configuration or accessibility. Examination of the steam generator primary nozzle safe-end pipe welds is limited both by the nozzle geometry and surface condition and the limited surface preparation on the pipe side of the weld. The surface on the pipe side of the weld, which is a cast elbow, is machined for a distance of approximately 3 inches from the surface Exaninations can be perfomed on the edge of the weld.
surface of the weld but are severely limited from the nozzle side by the rough, as-cast surface. Surface examinations can be performed on 100% of the weld and the base metal on the pipe side.
Evaluation Because of the geometric configuration and lack of surface preparation of the areas around these welds, it is considered impossible to obtain meaningful results on 100% of the volumes required to be examined by the Code. The licensee has proposed to examine the required volumes to the extent practical and to perform the surface examination in accordance The staff has determined that the with the Code requirements.
proposed examination will cover a sufficient percentage of the required volume to provide assurance that unacceptable flaws do not exist and the 100% surface examination will provide further assurance of the structural integrity of the safe end-to-pipe wel ds. We conclude that relief from the Code requirements may be granted as requested.
4.
Request relief from 100% volumetric examination of the following piping welds:
(ItemB4.5,ExaminationCategory B-J )
(a) Loop 1 Cold Leg Low Head SIS; Weld No. 7 (b) Loop 1 R.T.D. Return Line; Weld No.12 (c) Loop 2 Accumulator Discharge Line; Weld No.1 (d) Loop 2 R.T.D. Return Line; Weld No.12 1687 305
. (e) Loop 3 Accumulator Discharge Line; Weld No.1 (f) Loop 3 R.T.D. Return Line; Weld No.12 (g) Pressurizer Relief Line; Weld No. 22 (h) Loop 3 Pressurizer Spray Line; Weld No. 33 (i) Longitudinal welds in the primary coolant loop which are fabricated from two halves of austenitic stainless steel castings and welded together by the electroslag process.
(j) Loop 1 Hot Leg Low Head SIS; Weld No.18 (k) Loop 2 Accumu.ator Discharge Line; Weld No. 9 (1) Loop 2 Cold Leg Low Maad SIS; Weld No.15 (m) Loop 3 Accumulator Discharge Line; Weld Nos.12 and 17 (n) Loop 3 Hot Leg Low Head SIS; Weld No. 9 (o) Pressurizer Relief Line; Weld No.11 (p) Loop 1 Pressurizer Spray Line; Weld Nos. 6 and 10 (q) Loop 3 Pressurizer Spray Line; Weld No. 36 (r) Pressuri?er Safety Valve Lines; Weld Nos. 8,17 and 26 Code Requirement Volumetric examination of all of the area of 25% of the circumferential joints incl ding the adjoining one-foot sections of longitudinal joints and 25% of the pipe branch connection joint's during the inspection interval.
Licensee Basis for Requesting Relief Limitations may occur for the volumetric examination of piping system circumferential butt welds (Category B-J) when the welds occur at geometric discontinuities such as 1687 306
\\
. pipe-to-vessel welds, pipe-to-fitting or fitting-to-fitting welds.
For pipe-to-fitting welds or pipe-to-vessel nozzle welds, volumetric examinations can be performed to the extent required by T-532 of Section V from the weld Volumetric examination from the fitting and pipe surfaces.
side would be dependent upon the geometric configuration.
Where elbows or tees are concerned, volumetric examination can be perfomed from the fitting side except where the intrados of the fitting prevents adequate ultrasonic coupling.
No volumetric examinations can be perfomed from the fitting side when it is a valve or a flange.
In all cases 100%
of the weld material can be examined.
In instances where welds occur at fitting-to-fitting, access restrictions as outlined above occur on both sides of the weld.
In instances where ultrasonic examinations cannot be performed on 100%
of the volume of the weld and heat affected zones, surface examinations will be perfomed to supplement the limited volumetric examination.
The 90-degree elbows in the crossover leg of the reactor coolant system are fabricated in two halves from austenitic stainless steel castings welded together by the electroslag The structure of the material is such that process.
ultrasonic examinations cannot be perfomed as required by IWB-2600. These welds will be subjected to a surface examination and a visual examination during system pressure tests.
In instances where the locations of pipe supports or hangers restrict the access for the volumetric examinations of pipe welds, examinations will be perforced to the extent practical unless removal of the support is pemissable without unduly stressing the system. These welds will be supplemented with a surface examination.
For those reactor coolant pipe welds which will be examined utilizing refracted longitudinal ultrasonic techniques or a technique which utilizes only a 1/2 node calibration, a surface examination will also be perfomed on the outside surface of the welds.
1681 307
. Evaluation The design of the reactor coolant loops and the materials from which portions of the loops were fabricated restrict full compliance with the examination requirements of the The licensee has proposed to volumetrically examine Code.
the welds to the extent practical and supplement the limited volumetric examination with a surface examination. The staff finds the combination of examinations proposed by the licensee acceptable in providing assurance of the structural integrity of the welds listed and conclude that relief from 100% volumetric examination may be granted.
5.
Request relief from 100% volumetric examnation of the reactor coolant system branch nozzle connection welds. (Item 84.6, Category B-J)
Code Requirement Volumetric examination of all of the area of 25% of the circumferential joints including the adjoining one-foot section of longitudinal joints and 25% of the pipe branch connection joints during the inspection interval.
Licensee Basis for Requesting Relief The configuration of the reactor coolant branch nozzle welds prevents the conduct cf meaningful UT examination.
Evaluation The design of the pipe branch connections prevents 100%
volumetric examination of the welds and heat affected zones.
Practical alternative techniques to volumetrically examine the entire areas of these welds which would produce meaningful results are not presently available. The licensee has proposed to volumetrically examine portions of the welds on which meaningful results can be obtained and to use 100% surface examination on these welds. The staff finds the proposed combination of examinations acceptable in providing assurance of the structural integrity of the piping branch connections and concludes that relief from the 100% volumetric examination requirement may be granted.
1687 308
. 6.
Request relief from volumetric examination of integrally-welded pipe supports. (Item B4.9, Examination Category B-16-1)
Code Requirement Volumetric examination of 25% of the integrally-welded supports during each inspection interval.
Licensee Basis for Requesting Relief These welds are fillet welds by design. Volumetric examination of this type of weld by ultrasonic testing method would not produce meaningful results.
Evaluation Because of the weld design, ultrasonic examination is an impractical technique to use.
Radiographic examination of these welds would be difficult to perform and interpret, and would therefore result in little added assurance of safety. The licensee has committed to subject these welds to surface examination and to volume-trically examine the base metal. Based on the loading conditions of these types of welds, flaws would most likely generate at the weld surface and thus be detectable by surface examination. Ultrasonic examination of ' te base etal would m
provide assurance that flaws in the bast. metal do nct exist.
The examination techniques to be employt d by the licensee are therefore considered acceptable in troviding assurance that the pipe suppc/f 3 integrity will be maintained during the inspection period.
7.
Request to delay volumetric examinatior of the reactor coolant pump seal houshg bolts until the end of the 10-year inspection interv al.
(Item B5.1, Inspection CateLory B-G-1)
Code Requirement Volumetric examination of 100'.' of bolt s while in pl:ce of volumetric and surface examination of 100% of bolts when removed. To be completed by the end of the inspection interval.
1687 309
9-Licensee Basis for Requesting Relief The reactor coolant pump seal housing bolts are of the socket head type and the configuration is such that ultrasonic examinations as required by IWB-2600 cannot be perfomed when the bolting is in place. Examinations will only be perfomed when the seal housing is disassembled at the end of the inspection interval.
Evaluation The design of the seal housing bolts prevents ultrasonic examination and radiography is an impractical technique to use with the bolting in place. To disassemble a reactor coolant pump at the frequency required in order to perfom the examination would place an undue burden on the licensee without providing a comparable increase in the level of safety of the facility. System leakage monitoring is presently perfomed and will provide some assurance of the condition of the seal housing bolts. We therefore conclude that the safety of the facility is not significantly decreased by delaying the required exanination to the end of the inspection interval and that relief from the require-ment may be granted for this inspection period.
In the event that a pump is disassembled for maintenance prior to the end of the interval, the Code required examination shall be perfomed at that time.
8.
Request relief frcm volumetric examination of pump casing welds if radiography cannot be perfomed.
(Item B5.6, Examination Category B-L-1)
Code Requirement Volumetric examination of 100% of pressure retaining welds in one pump of each group during the interval. The examination may be perfomed at or near the end of the inspection interval.
Licensee Basis for Requesting Relief Volumetric examinations as requi, ed by IWB-2600 will be attempted utilizing radiographic techniques. The success of these exaninations will be dependent upon the availabil-ity of high energy gamma sources and the level of background radiation.
Internal fittings in the pump may also provide restriction to the extent of examination that can be pertonned.
1687 310
. Evaluation The required volumetric examination by radiography has not In the event been determined to be impractical at this time.
that this detemination is made and the licensee submits to the Commission supporting infomation of his determinations, the staff will evaluate the infomation and issue its findings at that time.
Request relief from perfoming surface examination on the 9.
bolting for the reactor coolant punp main flange and loop stop valve bonnet bolting until the end of the 10-year interval when the pump or valve is disassembled.
(Items B5.1 and B6.1, Examination Category B-G-1)
Code Requirement _
The bolts shall be examined 100% by volumetric and surface methods during each inspection interval. The bolting may be volumetrically examined either in place under tension, when the connection is disassembled, or when the bolting is removed. The bolting shall be surface examined when remov ed.
Licensee Basis for Requesting Relief The bolting will only be removed at the end of the 10-year interval when the pump or valve is disassembled for the perfomance of the required casing and weld examinations.
Evaluation The perfomance of the recuired volumetric examination at the specified frequencies and the perfomance of a surface examination when the bolting is renoved is in compliance with Code requirements. Therefore, relief from the require-ments is not necessary.
B.
Class 2 Components 1.
Request relief from perfoming volumetric examination in full compliance with Section XI on those items where scanning 1687 311
. using ultrasonics is either not possible or not practical due to geometric configuration or accessibility of the welds.
Code Requirement _
Categories C-F and C-G require examination of 100% of the welds selected by volumetric techniques.
Licensee Basis for Requesting Relief Examinations of Class 2 piping system welds occurring at geometric discontinuities is limited and some limitations may be expected at all locations. For pipe-to-fitting or pipe-to-vessel nozzle welds, examinations can be perfomed to the extent required by T-523 of Section V from the weld and pipe surfaces.
Meaningful examination from the fitting side would depend upon the geometric configuration. Where elbows or tees are concerned, examination can be perfomed from the fitting side except where the intrados of the fitting prevents adequate ultrasonic coupling. No examinations can be perfomed from the fitting side when it is a valve or a flange.
In all cases 100% of the weld material can be examined.
In instances where welds occur at fitting-to-fitting, access restrictions as outlined above occur on both sides of the weld.
In instances where ultrasonic examinations cannot be perfomed on 100% of the volume of the weld and heat affected zone, surface examinations will be perfomed to supplement the limited volumetric examination.
Preservice examinations were not conducted on the welds in Class 2 systems in the Beaver Valley Unit 1 plant and the following listing of welds are those where it is expected that supplemental surface examinations would be required:
Loop 1 Main Steam ISO #DLW 2-2110 Weld #17 Loop 2 Main Steam ISO #DLW 2-2111 Weld #17 Loop 3 Main Steam ISO #DLW 2-2112 Weld #17 RHR System ISO #DLW 2-2310 Welds #18,19, 20, 40, 41, 42, 68 & 77 RHR System IS0#DLW 2-2311 Welds #2, 8, 23 & 26 RHR System IS0#DLW 2-2312 Welds #6 & 26 Charging Pump ISO #DLW 2-2410 Welds #4,16, 22, 34, Suction 40, 52 & 73 1687 312
, The code does not require that all welds in multiple streams be examined and consequently not all the welds listed above will be included in the inspection program.
Evaluation The design of the Class 2 piping system and the geometric configurations existing at fittings and nozzles prevent full compliance with volumetric examination requirements of the Code. The licensee has proposed volumetric examination in accordance with the Code to the extent that meaningful results are obtained and to perform a surface examination to supplement or complete 100% of the required areas to be examined. The staff finds the combination of examination nethods acceptable in providing assurance of the structural integrity of the welds and heat affected zones of the systems listed. We conclude that the proposed combination of examination methods will provide an adequate level of assurance of the safety of these systems and that rel f ef from the Code requirement, as requested, may be granted.
2.
Request relief from the 100% volumetric examination requirement of the Regenerative Heat Exchanger shell-to-tube sheet welds and request to examine 10% of the total of one head-to-shell weld and 10% of one shell-to-tube sheet weld on the Regenerative Heat Exchanger during each 40-month period.
(Item Cl.1, Examination Category C-A)
Code Requirement Volumetric examination of at least 20% of each circumferential weld, uniformly distributed among three areas around vessel circumference over the service lifetime of the component.
Licensee Basis for Requesting Relief The location of support members on the regenerative heat exchanger may prevent ultrasonic examinations being perfomed to the extent required by IWC-2600.
Examinations will be performed to the extent practical unless support components can be removed to provide additional access.
1687 313
f The regenerative heat exchanger is a three pass vessel, having a total of six head-to-shell welds and six shell-to-tubesheet welds.
In view of the high radiatior levels generally associated with this vessel, it is proposed that examinations be limited to 10% of the total of one head-to-shell weld and 10% of one shell-to-tubesheet weld during each 40-month period rather than a much smaller percentage of each of 12 welds.
Evaluation The design of the supports on the regenerative heat exchanger prevents ultrasonic examination of the shell-to-tubesheet welds to the extent required by the Code. Radiography is an impractical examination method.
The licensee has proposed to use surface and visual examination in lieu of the required volumetric on areas which 3re inaccessible for ultrasonic exami nation.
Because of the design and conditions to which these welds are subjected, surface flaws are most likely to be generated and the surface and visual examination as proposed by the licensee is an acceptable examination technique for detection of such flaws.
Because of the relatively high radiation levels in the areas of examination and the small percentage of each head-to-shell and shell-to-tubesheet weld to be examined to the Code requirement, the staff finds that the requirement is impractical and will not provide a significant increase in assurance of the heat exchanger's structural integrity over the examination proposed by the licensee.
We therefore conclude that the examination of 10% of one weld each 40-month period as proposed by the licensee exceeds code requirements and provides adequate assurance of the heat exchangers structural integrity.
Relief from the Code requirement as requested may be granted.
3.
Request relief from volumetric exanination of nczzle-to-vessel welds on the residual heat exchanger.
(Item Cl.2, Examination Category C-B)
Code Requirement Volumetric examination of 100% of the nozzle-to-vessel attachment weld over the service lifetime of the component 1687 514
. Licensee Basis for Requesting Relief The residual heat removal heat exchanger nozzle-to-vessel weld are covered by a reinforcement ring and are not accessible for examination as required by IWC-2600.
Evaluation Because of the reinforcement ring required in the design at openings in the component shell, the nozzle-to-vessel weld is completely inaccessible for voltnetric or surface examination. Disassembly of the component to perfom the required examination is impractical during refueling outages because of the importance of the heat exchanger's function at that time. The staff recommends that relief from the examination requirements to be granted provided the nozzle and reinforcement ring areas are visually inspected during the inspection period.
In the event the residual heat removal heat exchanger is disassembled for maintenance and the welds are accessible for examination from the inside surface, the Code required examination shall be performed.
We conclude that the recommeded visual inspection will provide adequate assurance that the vessel shell integrity at the nozzle location is maintained during the inspection period.
4.
Request relief from volumetric examination required by IWC-2600 for the following:
Seal Water Return Filter: cover-to-shell and head-to-shell welds, and integrally-welded supports Seal Water Injection Filter: head-to-shell and shell-to-tubesheet welds and integrally-welded supports Reactor Coolant Filter:
cover-to-shell and head-to-shell welds and integrally-welded supports.
(Items Cl.1 and C1.3, Examination Category C-A and C-C)
Seal Water Injection Filters:
Pressure Retaining Bolting (Item C1.4, Examination Category C-D) 1687 315
Code Requirerpent, Volumetric examination of at least 20% of each circumferential weld, uniformly distributed among three areas around the vessel circumference over the service lifetime of the component. Visual and either surface or volumetric examination of pressure retaining bolting.
Licensee Basis for Requesting Relief The filters will have to be removed to allow the required examination to be performed. With the filers in place, the expected levels of radiation wot.ld be 6-10 R/hr. The removal of the filters exposes station operational and maintenance personnel to substantial whole body doses (300-500 mr/ man). Approximately 0.75 man-hour is needed to perfom examinations on one complete filter and based on an exposure rate of 500 mr/hr following cartridge removal, examination of one filter would involve 375 man-rems exposure. Addit ioal exposure would be associated with insulation removal and replacement.
In view of the above problems associated with high radiation exposure to personnel and the very limited requirement for extent of examination, relief is requested from performing any examination on the CVCS filters other than visual for evidence of leakage during system pressure tests. As further justification for deleting any NDE requirement on these com-ponents it should be noted that the complete piping system in which they are contained, being 4 inch diameter or less, is exempt from any examination requirement of IWC-2520 by IWC-1220 (d).
Evaluation The licensee has stated that these filters are changed when needed, based on measured differential pressures. The expected frequency of filter change is:
Seal Water Return Filter (once/3-4 years)
Seal Water Injection Filters (once/3-4 years)
Reactor Coolant Filter (once or twice/ year) 1687 H6
. An examination of the welds can be performed at essentially the frequency required by the Code.
The staff recognizes the radiation exposure problem in perfoming the required volumetric examination and recomend a surface examination be substituted for the volumetric examination.
The surface examination will reduce the exposure time to personnel by about one-half as well as provide assurance of the structural adequacy of the vessels, bolts, and supports and the condition of the connecting pipes.
We find that relief from the volumetric examination as required by the Code may be granted.
Pressure retaining bolting may be either volumetric or surface examined, therefore, surface examination as described above will meet the requirements of the Code.
5.
Request relief from volumetric examination requirement for the shell-to-flange weld and head-to-shell weld of the seal water heat exchanger.
(Item C1.1, Examination Category C-A)
Code Requirement Volumetric exanination shall cover at least 20% of each shell and head circumferential weld uniformly distributed among three areas around the vessel circumference to be performed over the service lifetime.
Licensee Basis for Requesting Relief The thickness of the materials utilized for the construction of this component (0.165 to 0.185 inches) is such that meaningful results could not be expected with ultrasonic examination as required by IWC-2600. The problems associated with the ultrasonic examination of thin wall materials has been recognized by Section XI of the Code and the requirement in subsequent addenda and editions (Winter 75 for Class 1 and Summer 76 for Class 2) revised to require surface examination of welds in components with wall thicknesses of 1/2-inch and less.
Surface and visual examination of these welds will be performed as an alternative method.
Evaluation The thickness of the material as well as the Code requirement to examine less than one-inch of length of each weld makes 1687 517
t l volumetric examination an impractical examination method.
Surface and visual examination as proposed by the licensee are adequate examination methods for the welds and base metal since flaws would most likely appear at the surface.
The staff concludes that the proposed alternative examinations will provide an acceptable level of quality and safety and therefore relief from the volumetric examination requirement may be granted.
Request to conduct the required examinations on the charging 5.
pump casing welds when the pump is disassenibled.
(ItemC3.1, Inspection Category C-F)
Code Requirement Volumetric examination of 1007, of the weld over the service lifetime.
Licensee Basis for Reouesting Relief Examination of the charging pump casing weld by ultrasonic, radiographic or surface examination requires complete disas-sembly of the pump casing and removal of the inboard seal It is requested that ultrasonic housing and rotor assembly.
examination be conducted whenever a pump is disassembled for maintenance reasons.
Evaluation To disassemble the charging pump in order to perform the required examination at the frequency specified in the Code is impract'ical.
Conduct of the examinations at the end of each inspection interval, which the licensee has agreed to if a pump is not disassembled prior to the end of the inspec-tion iriterval, meets the intent of IWC-2411 and is therefore acceptable., The staff finds that relief from the examination frequency will not significantly decrease the plant's operational safety and concludes that relief from the examination frequency requirement, as requested, may be granted.
7.
Augmented Inspection Requirements Portions of Class 2 systems and components are exempt from These the examination requirements of IWC-2520 by IWC-1220.
systems and components are listed below:
1687 318
i (a) CVCS Piping equal to or less than 4-inch nominal diameter is exempted by IWC-1220 (d).
(b) The Boron Injection System piping is equal to or less than 4-inch nominal diameter and exempted by IWC-1220 (d).
(c) During plant operation, the bcric acid solution will be constantly recirculated through the boron injection tank by the transfer pump system. Samples would normally be taken on a regular basis and the component exenpt from examination by IWC-1220 (c).
(d) During plant operation, the contents of the SIS accumu-lators are normally sampled on a regular b? sis and this component and associated piping would also be exempted by IWC-1220 (c).
(e) The high head SIS piping is equal to or less than 4-inch nominal diameter and exenpted by IWC-1220 (d).
(f) During plant operation, the high head SIS injection pumps are run on a periodic basis to recirculate flow to and from the RWST. Samples taken on a regular basis from the RWST would verify the chemistry of the system fluid and exemption from examination would again be by IWC-1220 (c).
(g) The containment spray system does not function during normal reactor operation and is exempted by IWC-1220 (b).
On June 27, 1979, we requested the licensee to submit an augmented inspection program for the systems discussed in items (c), (d), (f),
and (g) above and justification for any proposed exemptions. These items perfom an " Emergency Core Cooling" function, and as shown above are exempt from inspection as provided in paragraph IWC 1220 (c) of the ASME B&PV Code Section XI,1974 Edition, including the Summer 1975 Addenda.
The examination requirements of IWC shall apply, including inspection of supports, when the systems maximum operating pressure and temperature are greater than 275 psig and 200+F, respectively, and the component connections, piping, assuciated valves, and vessels (and their supports) are greater than 4-inch nominal pipe size.
1687 319
. The examination frequency and method shall be as described in the " Requirements for Class 2 Components," Subsection IWC,Section XI,1974 Edition, including the Summer 1975 Addenda.
The bases for requiring these systems to be inspected are:
(a) The systems are necessary for safe shutdown of the reactor in the event of an accident; (b) No technical justification exists for exemption from the examination requirements based on chemistry sampling, and (c) Examination of the systems in accordance with IWC-2520 provides assurance of the structural integrity of these systems which are vital safeguards for plant and public safety.
On August 10, 1979, the licensee committed to an augmented inspection program for these systems. Although no exemptions were requested, the licensee stated that any request for exemption would be made by the end of the Fall 1979 refueling. We find this acceptable.
C.
System Pressure Tests 1.
Request relief from testing and portions of the systems listed bel ow:
(a)
R.C. pump seal bypass line from check valves 191, 192 and 193 to M0 valve 307.
(b)
R.C. pump leak off line to manually operated valves 211, 212 and 213, 202, 205, 206, 346, 347 and 348.
(c)
R.C. pump seal injection line from check valve 181, 182 and 183 to MOV 308 A, B and C.
(d) Excess letdown from valve 201 to HCV 137.
(e) Letdown line from valve LCV 460B to orifice outlet valves 200 A, B and C.
(f) Pressurizer steam space sampling line from valve 64 to 65, pressurizer liquid space sampling line from valve 545F to SS108, and loop sampling lines from valves 1, 8, 6, and 10 to valves SS106 A, B, C, and D.
1687 320
. Code Requirement The pressure retaining components shall be subjected to a hydrostatic test at 1.25 times the systen design pressure at 100 F at least once toward the end of each inspection i nte rval.
Licensee Basis for Requesting Relief Subsections IWB and IWC contain differing requirements for the hydrostatic testing of Class 1 and Class 2 systems and components. The implerentation of these requirerents is impractical when the only means of pressurizing the Class 2 system is through the Class I system or when the boundary between the two systems is a check valve arranged for fitw from Class 2 to Class 1 systems.
Exception is taken to the performance of the hydrostatic test requirements as required by Article IWC-2412 (a) on those portions of the Class 2 systems identified above.
Evaluation Each of the 1isted portions of the Class 2 systers has a design pressure of 2485 psig. The operating pressure of the reactor coolant system is 2235 psig. To meet the requirements of IWC-5220 (a), each line ould have to be tested at a pressure of 1.05 x 2485 at 500 F, i.e., 2609 psig.
To meet the requirements of IWB-5221, the lines would require testing at 1.02 x 2235 at 500*F, i.e., 2280 psig.
The six portions of systems involved either cannot be isolated from the Class I systems or can only be pressurized through the Class I systems.
The licensee has agreed to conduct visual examinations for evidence of leakage on these portions of the above systems at the system noninal operating pressure in accordance with the requirements of IWB-5221 for the adjoining Class 1 systen.
In addition, the staff recommends that in those areas where it is possible to pressurize the Class 2 system in con-junction with the Class I system that a visual examination of these systems be performed during the Class I system hydrostatic test.
We conclude that this procedure is acceptable in providing evidence of leakage.
1687 321
. Request relief from the requirement of a visual examination 2.
of Class 1 systens and components listed below for evidence of leakage during the system pressure test following each refueling.
Cold leg injection from accumulators between check valves 48, 49, 50, 51, 52 and 53, test lines to valves 850 B, D and F and RHR return lines to valves 720 A and B.
Hot leg low head injection between check valves 20, 21 and 22 and 15,16 and 17 and high hetd injection to check valves 83 and 84.
Cold leg low head injection between check valves 23, 24 and 25 and 10,11 and 12 and boron injection to check valves 100, 101 and 102.
RHR take-off line between nomally closed (with pressure interlock) valves 700 and 701.
Code Requirement The pressure retaining components shall be subjected to a hydrostatic test at 1.10 times the system operating pressure at least once toward the end of each inspection interval and a leakage test at operating pressure following each outage.
Licensee Basis for Requesting Relief During nomal plant operation the portion of the cold leg injection from accumulators between check valves 48, 49, 50, 51, 52 and 53, test lines to valves 850 B, 0 and F and RHR return lines to valves 720 A and B is pressurized to the nomal accumulator operating pressure of 585 to 681 psig.
The portions of the hot leg low head injection between check 20, 21, 22 and 15,16 and 17 and high head injection valves to check valves 83 and 84 are filled and vented but not This portion of the pressurized during nomal operation.
system can be pressurized by diverting charging pump discharge flow through the high head safety injection path by opening notor operated valve 869 A or B.
1687 322
. The portions of the cold leg low head injection between check valves 23, 24 and 25 and 10,11 and 12 and boron injection to check valves 100,101 and 102 are filled and vented but not pressurized during nomal operation. This portion of the system can be pressurized by diverting charging pump discharge flow through the high head safety injection path by opening valve 836.
The portions of the RHR take-off line between normally closed valves 700 and 701 will be pressurized whenever the system is put into operation during plant shutdown when the reactor coolant system is cooled to 350+F and depressurized to 450 psig. These valves are interlocked to automatically isolate when reactor coolant system pressure exceeds 630 psig.
However, the pressure tests of the high head safety injection system can only be performed when the reactor coolant system is at sufficiently high pressure to naintain the first check valve closed. Under these conditions there would be very high potential for overpressurizing the primary system and this test is not recommended.
Evaluation The design of the systems prevents pressurizing the portions The of piping listed during the system pressure test.
licensee has committed to perfom alternate tests and has agreed to perfom a visual inspection of these systems prior to each refueling shutdown. We find the alternate inspections acceptable and conclude that relief from visual inspection of these systems for evidence of leakage during the system pressure test following refueling should be granted.
D.
General Request that calibration blocks be made to the requirements of 1.
Article T-434.1 in Winter 1976 Addenda of Section V in lieu of I-3121 of Section XI.
Basis for Requesting Relief The reason this alternative is requested is that the Code requires that calibration blocks for the examination of 1687 523
( welds in ferritic vessels 2-1/2 inches thick and greater be fabricated f rom material taken from the component nozzle drop out or material from the component prolongation. As a third alternative, when it is not possible to fabricate that block from material taken from the component, the block may be fabricated from a material of a specification included in 1he applicable examination volumes of the component.
It is required that the acoustic velocity and attenuation of such a block be demonstrated to fall within the range of straight beam longitudinal wave velocity and attenuation found in the unclad components.
For the components in Beaver Valley Unit 1, particularly the pressurizer and steam generators, it will be impossible to Materials of meet the requirements of alternatives I or 2.
the specification are readily available, but because all the components involved are clad on the inner surface, it would be impossible to obtain a comparison of sound beam velocities and attenuations in the unclad component.
Evaluation Since there is no material available from a drop out or component prolongation, the licensee has comitted to fabricate the calibration block from a material of the same specification, product form and heat treatment as the materials being j oined. This is in accordance with T-434.1.1 of the Winter 1976 Addenda of Section V.
We agree that the requirement of I-3121 that requires the acoustic velocity and attenuation of the block to be demonstrated to fall within the ranges found in the unciad components is inpractical since these components are clad. We have evaluated this request and consider it acceptable.
2.
Request to apply the Acceptance Standards as provided in Article IWB-3000 of the 1977 Edition of ASME Section XI for those areas which are in the course of preparation as defined in the 1974 Section XI including the Summer 1975 Addenda.
Code Requirements Where acceptance standards for a rarticular component or Examination Category are in the ccurse cf preparation, 1687 324
. evaluation shall be made of any indications detected during any inservice examination that exceed the acceptance standards for materials and welds specified in the Section III edition applicable to the construction of the component in order to determine disposition.
Licensee Basis for Requesting Relief Articles IWC-3000 and IWD-3000 entitled, " Evaluation of Examination Results," are in the course of preparation by the Code Committee and, as yet, are not available for use as defined in the 1974 Edition of Section XI with Addenda through Summer 1975. The rules of Article IWB-3000 of the 1977 Edition of Section XI will be utilized.
Evaluation The rules of IWB-3000 of the 1977 Edition of Section XI are more appropriate for evaluation of service induced defects than the construction code. The construction codes are outdated and are not consistent with inservice inspection standards. The staff's position is that the acceptance standards as defined in the 1977 Edition of Section XI are acceptable and may be applied in those cases where the acceptance standards in the 1974 Code, Sumner 1975 Addenda, are in the course of preparation.
3.
Request to use Appendix III of Section XI in lieu of Article 5 of Section V as a guidelines for piping weld inspection.
Basis for Reauesting Relief This alternative is requested because the Code provides no other guidelines for the inservice examination of piping wel ds.
Evaluation' IWA-2232 of Section X states that where Appendix I is not applicable, the provisions of Article 5 of Section V shall 1687 325
i apply regarding ultrasonic examinations. Appendix III of Section XI, Winter 1975 Addenda, provides rules for ultra-sonic examination of ferritic steels and Supplement 7 provides additional guidance for examination of austenitic welds.
Therefore, the use of either Article 5 or Appendix III is acceptable.
Summary Based on the evaluations of the requested reliefs from the Code requirements it is concluded that the Beaver Valley Unit 1 Inservice Inspection Program meets the requirements of the 1974 Edition through Sumner 1975 Addenda of the ASME Section XI Code to the extent practical and thus is in compliance with 10 CFR 50.55a (g).
Environmental Consideration We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the anendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 551.5(d)(4), that an environmental impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of this amendment.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date: December 4,1979 1687 326
2 e
lb EN 2
2 2
a T
VO II D TTE 2
4 4
5 5
AAR 1
1 1
NNI EMQ e
e e
e e
e e
e RI U s
s s
TAE t
t t
t t
t t
t LXR o
o o
o o
o c
o AE N
N N
N N
N N
N 1
e g
a P
e ON c
c c
c c
c cc c
NT i
i i a i
TM r
r r
r r
r rf r
I E i
i i
i EAE t
t t
t t
t t r t
DNR e
e e
e e
e eu e
OI I m
m m
m m
m mS m
CMU u
u u
u u
u u
u l
l l
l l d l
XE o
o o
o o
o on o
AQ l
l ER V
V V
V V
V Va V
s s
s s
d d
d d
le d
d l
l l
D d
e e
e dW l
l e
e W
W W
n E
l ae N
o e
la W
l W
e l
l e
p I
t W _.
o l cl ecl e
e p
l i M
n aP A
g l
l X
n a
ei esa P sa s
s i
E i
i ed eii ii s
s P
i Rtt Pi PDt dDt e
e tl E
nn r
n a
n V
V o
na t
en B
d ee d e doe eoe ri amr aM) at r Ht r o
o MS O
ege e
6 e
e e
t t
d ed n
f u AT T
H ef Ht(
Htf etf R N S m n
nm rnm e
e E
mt ui GE A
r u
res reu ueu l
l 1 0N E
el c emd emc smc z
z e
cg RO R
wer x gl wgr ogr z
z f
r r.
TD P A
oei
- ee oei l ei o
o a
i o I
N S
CL NNO UOC 7
7 6
6 I
i 9
9 1 YT1 t
ELES L
I 8
8 8
8 6
7 1
1 EC E
0 LLPS B
T 6
6 6
6 6
6 BASA EA C
W W
W W
W 5
AVNL DCOU A
A A
A A
A 1
1 T
I C OITR
- 8 8
- 8
- 8 5
5 R
CL T
I 6 I6 I6 I6 I6 I6 1
1 EEE P
S I 9 I9 I9 I9 I9 I9 3
3 I1 I1 B
B VCD P
N I 1 I1 I1 I 1 AI O A
O EVC C
BREE SM NS I A TN
)
E se N
rd e
e O
oi r
r P
l l
l l
tS u
u M
e e
e e
a s
s O
s s
s s
C s
s s
s r
ry s
s e
e e
e e
er e
e R
V V
V V
z na r
r i
em P y P y r
r r
r r
Gi r
r O
M o
o o
o u
r ga ga E
t t
t t
s mP nd nd T
c c
c c
s a(
i n i n S
a a
a a
e e) pu p u Y
e e
e e
r t3 i o i o S
D R
R R
P S(
PB PB NO 0I Y E0TR B2NG B
B B
B D
D F
J L5AO A - I E TBMT B
B B
B B
B B
B WAA I XC E
0 E6N 2
2 2
2 2
2 1
5 0O L2 2
3 4
4 B - M l
l l
l ABE B
B B
B 8
B B
B TWT I I "j
h3N l' ((
3 CC
Page 2 TABLE 1 (CONTINUED)
TABLE CODE TABLE IWB-2500 APPLICABLE CODE ALTERNATIVE IWB-2600 EXAMINATION TO EXAMINATION EXAMINATION
! TEM NO.
CATEGORY SYSTEM OR COMPONENT CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUIRED B4.6 B-J Piping Pressure B 31.1, 1967 Branch Pipe Connection Volumetric Note 5 Boundary Welds Exceeding 6-inch Diameter B4.9 B-K-1 Piping Pressure B 3.1., 1967 Integrally Welded Volumetric Note 6 Boundary Supports B5.1 B-G-1 Reactor Coolant I II-A, 1968 Pressure Retaining Volumetric -
Note 3 Pump Bolts - Seal Housing In Place Bolts System Pressure Cold leg injection Vis ual / Hydro-Note 15 Tests from accumulators static Pressure Class 1 Components between check valves 48, 49, 50, 51, 52, and 53, test lines to valves 850 B, D-and F and RHR return lines to valves 720 A and B.
System Pressure Hot leg low head Visual / Hydro-Note 16 Tests injection between static Pressure Class 1 Components check valves 20, 21 and 22 and 15,16 and 17 and high head injection to check valves 83 and 84.
-^
Ch CO System Pressure Cold leg low head Vi sual / Hydro-Note 16
'd Tests injection between check static Pressure t,q Class 1 Components valves 23, 24 and 25 and ps) 10,11 and 12 and boron cx3 injection to check valves 100,101 and 102.
Page 3 TABLE 1 (CONTINUED)
TABLE CODE TABLE IWB-2500 APPLICABLE CODE ALTERNATIVE IWB-2600 EXAMINATION TO EXAMINATION EXAMINATION ITEM NO.
CATEGORY SYSTEM OR COMPONENT CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUIRED System Pressure RHR take-off line Visual / Hydro-Note 17 Tests between normally static Pressure Class 1 Components closed (with pressure interlock) valves 700 and 701.
CD
~J
~
N W
Page 4 TABLE 1 (CONTINUED)
BEAVER VALLEY UNIT 1 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 2 COMPONENTS TABLE CODE TABLE IWB-2500 APPLICABLE CODE ALTERNATIVE IWB-2600 EXAMINATION TO EXAMINATION EXAMINATION ITEM NO.
CATEGORY SYSTEM OR COMPONENT CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUIRED C1. 2 C-B Residual Heat IIIC Nozzle to Vessel Welds Vol umetric Note 9 Exchangers (2)
(Tube Side)
RH-E-1 A & IB Cl.1 C-A Seal Water IIIC Cover Weldment to Shell Volumetric Note 10 Return Filter Weld CH-FL-3 Cl.1 C-A Seal Water IIIC Head to Shell Weld Volumetric Note 10 Return Filter CH-FL-3 Cl. 3 C-C Seal Water IIIC Integrally Welded Surface Note 10 Return Filter Supports CH-FL-3 C1.1 C-A Seal Water Heat IIIC Shell to Flange Weld Volumetric hte 11 Exchanger CH-E-1 Head to Shell Weld Volumetric Note 11
&co Cl.1 C-A Ragenerative Heat IIIC Head to Shell Welds (6) Volumetric Note 7 N
Exchanger CH-E-3 u
u O
Cl.1 C-A Regenerative Heat IIIC Shell to Tubesheet Vol umetric Note 8 Exchanger Welds (6)
CH-E- 3
Page 5 TABLE 1 (CONTINUED)
TABLE CODE TABLE IWB-2500 APPLICABLE CODE ALTERNATIVE IWB-2600 EXAMINATION TO EXAMINATION EXAMINATION ITEM NO.
CATEGORY SYSTEM OR COMPONENT CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUIRED Cl.1 C-A Regenerative Heat IIIC Head to Shell Welds (6) Volumetric Note 7 Exchanger CH-E-3 C1.1 C-A Regenerative Heat IIIC Shell to Tubesbeet Vol umetric Note 8 Exchanger Welds (6)
CH-E-3 C1.1 C-A Seal Water Injec-IIIC Head to Shell Weld Volumetric Note 10 tion Filters (2)
CH-FL-4 A & 4B Cl.1 C-A Seal Water Injec-IIIC Shell to Flange Weld Vol umetric Note 10 tion Filters (2)
CH-FL-4A & 4B C1. 3 C-C Seal Water Injec-IIIC Integrally Welded Surface Note 10 tion Filters (2)
Supports CH-FL-4 A & 4B Cl.4 C-D Seal Water Injec-IIIC Pressure Retaining Visual and Note 11 tion Filters (2)
Bol ting Volumetric CH-FL-4A & 4B tu
'd Cl.1 C-A Reactor Coolant IIIC Cover Weldment to Vol umetric Note 10 Filter Shell Weld
[jj CH-FL-2
Page 6 TABLE 1
( CONTINUED)
TABLE CODE TABLE IWB-2500 APPLICABLE CODE ALTE?'JTIVE IWB-2600 EXAMINATION TO EXAMINATION EXAM:'JTION ITEM NO.
CATEGORY SYSTEM OR COMPONENT CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT PEQU:3ED Cl.1 C-A Reactor Coolant IIIC Head to Shell Weld Volumetric Note 10 Fil te r.
CH-FL-2 C1.3 C-C Reactor Coolant IIIC Integrally aelded Surface Note ':
Filter Supports CH-FL-2 C2.1 C-F; C-G Piping Systems B31.1 Circumferential Butt Volumetric Note 5 Welds C2.3 C-F; C-G Piping Systems B 31.1 Branch Pipe to Pipe Vol umetric Note 5 Welds C3.1 C-F Centrifugal Charg-Pump Casing Welds Vol umetric Note 12 ing Pumps (3)
CH-P-1 A,1B & 1 C System Pressure Tests R.C. pump seal bypass Visual / Hydro-Note 13 Class 2 Components line from check valves static Pressure 191,192 and 193 to M0 valve 307.
Os System Pressure Tests R.C. pump leak off Vi s ual / Hydro-Note 'I Class 2 Components line to r.anually static Pressure
(,q operate valves 211, q,4 212 and 213, 202, 205, rs) 206, 346, 327 and 348.
Page 7 TABLE 1 (CONTINUED)
TABLE CODE TABLE IWB-2500 APPLICABLE CODE ALTERNATIVE IWB-2600 EXAMINATION TO E XAMINATION EXAMINATION ITEM '40.
CATEGORY SYSTEM CR CCv:CNENT CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUIRED System Pressure Tests R.C. pump seal injec-Vis ual / Hydro-Note 13 Class 2 Components tion line from check static Pressure valve 181,182 and 183 to M0V 308 A, B and C.
System Pressure Tests Excess letdown from Visual /Hyd ro-Note 13 Class 2 Co ;;r.ents valve 201 to HCV 137.
static Pressure System Pressure Tests Letdown line from Visual / Hydro-Note 13 Class 2 Components valve LCV460B to static Pressure orifice outlet valves 200 A, B and C.
System Pressure Tests Pressurizer steam Vis ual / Hydro-Note 13 Class 2 Components space sampling line static Pressure from valve 64 to 65, pressurizer liquid space sampling line from valve 545F to SS108, and loop sampling lines from valves 1, 8, 6, and 10 to valves SS106 A, B, C, and D.
CO N
V4 V4 V4
Page 8 TABLE 1 (CONTI..JED)
BEAVER VALLEY UNIT 1 INSERVICE INSPECTION PROGRAM GENERAL REQUIREMENTS TAB LE CODE TABLE IWB-2500 APPLICABLE CORE ALTERNATIVE IWB-2600 EXAMINATION TO EXAMINATION EXAMINATION ITEM NO.
CATEGORY SYSTEM OR :CMPONENT COLSTRUCTION AREA TO EE EXAMINED REQUIREMENT REQUIRED Calibration Blocks Welds in Ferritic I-3121 of Note 14 Vessels 2-1/2 inchesSection XI thick and greater.
Acceptar.ce Standards Class I Co :caents 1974 thru 1977 Addition Summer 1975 Addenda Pipe Weld Inspections Ultrasonic Examinations 1974 thru Winter 1975 Summer 1975 Addenda Addenda e
wwe CD N
LN U
4
}D**
'9 co o
- a 1.
Examination to be performed on the, u;ide of the vessel between adjacent incore instrumentation penetrations provided radiation levels permit such examinations (not to exceed whole body dose of 1250 mr in order to complete any one examination).
Examine 60% of one meridional weld and 5% of the adjacent portion of each circumferential weld.
?.
VI'.ual examination o f welds for evidence of leakage during the perf ormance of ry, tem hydros tatic test s shall be performed.
3.
Volumetric and surface examination of 100% of the bolts when removed for pump disassembly for maintenance and/or at the end of the 10 year inspection interval whichever occurs first.
4.
Integrally cast nozzle-to-head configurations will be visually examined at the radiused sections.
5.
Volumetric examination is required to the extent practical.
Where less than 100% or required volumetric examination is used, supplemental 100% surface examination is required.
Examinations utilizing refracted longitudinal ultrasonic techniques or a technique which utilizes only a 1/2 node calibration will be supplemented by a surface examination.
6.
Surface examination of weld surfaces and volumetric examination of base metal is required.
7.
10% of the total one weld shall be examined during each 40 month period.
8 Volumetric examination is required on all areas to the extent applicable and practical. Surface and visual examination is required on areas inaccessible for ultrasonic examination.
9.
Visual inspection of the nozzle and reinforcement ring areas is required during the inspection period.
Code required examin-ation is required in the event the RHR heat exchanger is disassembled for maintenance or other reason.
10.
Surface examination is required of the vessel, supports and connecting piping.
- 11. Surface and visual examination is required.
12.
Volumetric examination will be performed during pump disassembly for maintenance or at the end of each inspection interval whichever occurs fir <,t,
13.
Code hydrostatic pre <.sure and visual examination on Class 2 systems where possible and/or visual examination on remaining Class 2 systems at the system nominal operating pressure in accordance with requirements of IWB-5221 for the adjoining Class 1 systems.
1687 735
TABLE 1 NOTES (CONTINUED) 14.
Calibration blocks will be in confonnance with Article T-434.1 in Winter 1976 Addenda of Section V.
- 15. Visual and hydrostatic pressure test will be performed i.o the accumulator operating pressure of 585 to 681 psig.
16.
Visual and hydrostatic pressure test will be performed at the normal reactor coolant system pressure using the charging pumps.
17 Visual and hydrostatic pressure test will be performed at a temp 6rature of 300-350"F and a pressure of 450 psig.
1687 336
TABLE 2 PIPING PRESSURE B0UNDARY CIRCUMFERENTIAL AND LONGITUDINAL PIPE WELDS (Specific Welds Identified in Item 84.5 From Table 1)
(a) Loop 1 Cold leg Low Head SIS; Weld No. 7 (b) Loop 1 R.T.D. Return Line; Weld No.12 (c) Loop 2 Accumulator Discharge Line; Weld No.1 (d) Loop 2 R.T.D. Return Line; Weld No.12 (e) Loop 3 Accumulator Discharge Line; Weld No.1 (f) Loop 3 R.T.D. Return Line; Weld Nd. 12 (g) Pressurizer Relief Line; Weld No. 22 (h) Loop 3 Pressurizer Spray Line; Weld No. 33 (i) Longitudinal welds in the primary coolant loop which are fabricated from two halves of austenitic stainless steel castings and welded together by the electroslag process.
(j) Loop 1 Hot Leg Low Head SIS; Weld No.18 (k) Loop 2 Accumulator Discharge Line; Weld No. 9 (1) Loop 2 Cold Leg Low Head SIS; Weld No.15 (m) Loop 3 Accumulator Discharge Line; Weld Nos.12 and 17 (n) Loop 3 Hot Leg Low Head SIS; Weld No. 9 (o) Pressurizer Relief Line; Weld No. 11 (p) Loop 1 Pressurizer Spray Line; Weld Nos. 6 and 10 (q) Loop 3 Pressurizer Spray Line; Weld No. 36 (r) Pressurizer Safety Valve Lines; Weld Nos. 8,17 and 26 1687 337
'