ML20083K659
| ML20083K659 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/25/1979 |
| From: | Counsil W NORTHEAST UTILITIES |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| TAC-8320, NUDOCS 7901300105 | |
| Download: ML20083K659 (83) | |
Text
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, NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE UNIT NO. 2 ESTABLISIMENT OF INSERVICE INSPECTION CRITERIA Revisions to 10 CFR 50.55a (g) set forth the inspection requirements for nuclear power plant components by referencing the ASME Boiler and Pressure Vessel Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components". Applicability of code addenda depends on the facilities' cmmercial operation date and the effective amendment to paragraph (b) of 50.55a.
Millstone Unit No. 2 commenced commercial operation on December 26, 1975.
Start dates for inspection periods in the first ten-year inspection interval are as follows:
(} First 40 months - December 26, 1975 Second 40 months -- April 26, 1979 Third 40 months - August 26, 1982 10 CFR 50.55a (g) (5) requires that licensees submit an application for re-vision to facility Technical Specifications for requirements which conflict' with the effective edition and addenda of ASME Section XI, six months before the start of each 40-month inspection period (20 months for pump and valve operational readiness tests, and system pressure tests). The effective edition of the code is the edition and addenda published in 50.55a (b); presently, the 1974 edition including those addenda through the summer of 1975 addenda (Federal Register, Volume 41, No. 235, December 6,1976).
Subsequent to the CFR revisions, the NRC Staff published guidance for complying
) with certain provisions of 10 CFR 50.55a (g) which requests that a . description
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1 v. 44 Paga 2 of the planned inservice inspection and testing program as well as any requests i for relief from ASME code requirements determined to be impractical be submitted I at least 90 days before the start of any inspection or testing period. '
Hi11 stone Unit No. 2 commences its second inspection period on April 26, 1979.
This submittal contains the Inservice Inspection Program description and request ,
for waivers for this period. The progran was developed' to the requirements of I the Summer 1975 Addenda and is applicable from April 26, 1979 ro August 26, 1982, for Inservice Inspection and to December 26, 1980 for operational readiness testing of pumps and valves and system pressure tests. '
The submittal is arranged in six sections, to be consistent with ASME Section XI.
In addition, a complete set of P&ID " Boundary Diagrams'.' are included' to. show system classification boundaries, and pump and valve locations.
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> -no-20C N ,f ,,, MILLSTONE UNIT 2 BOUNDARY DIAGRAM P
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n i t s"ONE _ h T2 BOL DARY DIAGRAM-N Evg}Igggpigg H jfjg,ggL g
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. DIAG. 25 CONTA0L TANKS TO CHARG-g ING PUMP SUCTION:
150 PSIG;250'F
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! PIPING & INST. DIAGRAM 25203<
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3., O CHILLED lx-84BI WAT ER MTROL -
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" BOUNDARY DIAGRAM REAC TOR COOLANT SYSTEM I NSERVICE t hSFRVICE PROGRAM "TJR -= "' te P'-
p'u svier's n=w n.e , _ - e tN gues l Ne{mse uvienons e, s,.Q r. 4. e'
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25703 26126 Shit 3 d=% Rat =E C =% 2% =O M:::L% Et lllllltllt
- l MILLSTONE UNIT NO. 2
[\ l g Inservice Inspection Program for ASME Code Class 1 Components
%./
The attached table provides a tabulation of the Class 1 pressure-retaining components (and their supports) that are subject to the inspec-tion requirements of Subsection IWB of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, and Addenda through Summer 1975.
This tabulation identifies the components to be inspected, the Section XI Examination Category, area to be examined, and the method of examination.
Relief from the inspection requirements of Subsection IWB is requested where these inspection requirenents have been determined to be impractical.
Where relief is requested, specific information is provided which identifies the applicable code requirement, justification for the relief request, ana the inspection method to be used as an alternative. Table IWB-2600 items that are not applicable to Millstone Unit 2 have also been listed and identified in the interest of completeness.
/ 'N (j The following provides further clarification concerning the Class 1 inservice inspection program:
(1) Repairs to Class 1 components will be conducted to the requirements of Article IWA-4000.
(2) The inservice inspection and testing programs outlined in the attached tabulation have been developed as a result of a design review. Should certain ASME Section XI Code requirements be dis-covered to be impractical due to unforeseen reasons during the process of performing inspections or tests, relief will ~ be requested from the specific Section XI Code requirement at that time.
(3) Radiation levels in certain areas or of certain components may be found to prohibit the access for operators or inspectors to perform the inspections or tests described in this program. If source n strengths cannot be reduced and access is still restricted by considerations of compliance with the requirements of Regulatory I-1
. .. . . .. .. 4 J
i Guide,s 8.8 and 8.10, relief will be requested from the specific )
Section XI Code requirements and alternative examination or test requirements be proposed.
1 (4) Ultrasonic examinations are required to be conducted in'accordance with the provisions of Appendix I and Article 5 of Section V as.
required by Paragraph IWA-2232. As an alternative to using Article 5 of Section V, NNECO proposes to use Appendix III of Section XI of the 1974 Edition, Winter, 1975, Addenda of the ASME Boiler and -
Pressure Vessel Code for ultrasonic examination of piping systems.
It is recognized that Appendix III of Section XI was issued in the Winter, 1975, Addenda and, as such, has not been officially recognized by the NRC by reference in 10 CFR 50. However, Appendix III is the first guideline that has been publ.ished in the ASME Codes for the ultrasonic examination of pipe welds and, as such, its use is essential.
(5) Examinations of hydraulic' snubbers will be conducted in accordance s
with Technical Specifications, Section 4.7.8.1, so is excluded from category B-K-E in the accompanying table.
f 1
= w r
w, 4 " I-20 -
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O O NORTHEAST NUCLEAR ENERGY COMPANY O~1 7 MILLSTONE UNIT NO. 2 INSERVICE INSPECTION PROGRAM - CLASS 1 COMPONENTS Table Table Section IWB-2600 IWB-2500 XI Item- Examination Examination Relief No. Category Components and Parts to be Examined Method Requested Section 1. Reactor Vessel and Closure Head Bl.1 B-A Longitudinal and circumferential shell Volumetric No - Note 1 welds in core region Bl.2~ B-B Longitudinal and circumferential welds in Volurretric No - Note 2 shell (other,than those of Category B-A and B-C) and meridional and circumferential
_ seam welds in bottom head and closure head 4,1 (other than those of Category B-C)
B1.3' B-C- Vessel-to-flange and head-to-flange circum- Volumetric No ferential welds
.Bl.4- B-D. . Primary nozzle.to-vessel welds and nozzle- Volumetric Yes - Note 3 to-vessel inside radiused section
.B1.5. _B-E Vessel Penetrations Including Control Rod Visual (IWA-5000) No
. Drive and Instrument Penetrations
~Bl .' 6 'B-F. Nozzle to. safe-end-welds Surface and No - Note 4 Volumetric Bl.7 B-G-1 Closure' studs, in place Volumetric No
.Bl.8 B-G-1 Closure studs and nuts, when removed Volumetric and No Surface B1.9. IB-G . Ligaments between threaded stud holes Volumetric No B1.10- B-G-1 C1'osure. washers, bushings . Visual No l
. _~ . - - - - .- - .- . _ _ _ _ _ _ _ _ _ _ _ _ - .
- Table Table Section -
IWB-2600 IWB-2500 XI Item Examination Examination Relief No. Category Components and Parts to be Examined Method Requested B1.11 B-G-2 Pressure retaining bolting, less than 2" Visual No Bl.12 B-H Integrally-welded vessel supports Volumetric No - Note 5 B1.13 B-I-l Closure head cladding Visual and Surface Yes - Note 6 or Volumetric
- Bl.14 B-I-l' ' Vessel cladding Visual Yes - Note 6 Bl.15 B-N-1 Vessel interior Visual No Bl.16 B-N-2 Interior ~ attachments and core support Visual No - Note 4 structures
' Bl.17 B-N-3 Core-support structures . Visual No 1
- )) 81.18' :B-0 Control rod drive housings' Volumetric No J
' Bl;19 'B-P. Exempted components Visual (IWA-5000) No Section 2. Pressurizer
< B2.11 B-B Longitudinal and circumferential welds Volumetric No B2.2' B-D Nozzle-to-vessel. welds and nozzle-to- Volumetric No vessel inside radiused section.
B2.3 8-E . Heater connections Visual (IWA-5000) No
. B2.4' .B-F. Nozzle-to-safe end welds Volumetric and No T Surface 82.5 B-G-1 Pressure-retaining bolts and studs, in Volumetric' No - Note 4 place 1
B2. 6 8-G-1 Pressure-retaining bolts and studs,lwhen Volumetric and No - Note 4 removed Surface a
e
~-
t . t
- Tabl e -- Table Section ,-
XI Item Examination Examination Relief No. Category Components and Parts to be Examined Method Requested F B2.7 B-G-1 Pressure-retaining bolting Visual No - Note 4 B2.8 B-H- . Integrally-welded vessel supports Volumetric No i
i
- -B2.9 B-I-2 Vessel cladding' Visual Yes - Note 6 B2.10 B-P Exempted components Visual (IWA-5000) No
.B2.11 B-G-2 Pressure-retaining bolting, less than 2" Visual No.
Section 3. Steam Generators
.. i L B3.1. B-B. Longitudinal and circumferential welds, Volumetric No ;
I including tube-sheet-to-head or shell
-welds on the primary side B3.2 B-D' Primary nozzle-to-vessel head welds and Volumetric No .
. nozzle-to-head inside radiused section e
.7,-
.a Primary nozzle to safe-end welds
-B3.3 -B-F Surface and No - Note 4 Volumetric B3.4 B-G-1" Pressure-retaining bolts and studs, in Volumetric No - Note 4 place B3.5 =B-G-1 Pressure-retaining bolts and studs, when' Volumetric and No - Note 4 removed Surface B3.6' B-G-1 Pressure-retaining bolting Visual No - Note 4
'B3.7 B-H. ' Integrally-welded vessel supports Volumetric No lB3.8? :B-I-2 LV essel cladding Visual Yes - Note 6 B3.9: ;B-P Exempted components . Visual (IWA-5000) No l ,
'B3.10- -B-G : Pressure-retaining bolting Visual -No y +W t _ . _ _ -- ry. t
I L
( '
(
(
i
~
Table Table Section .-
IWB-2600 IWB-2500 XI Item Examination Examination Relief No. Category Components and Parts to be Examined Method Requested Section 4. Piping Pressure Boundary B4.1 B-F Safe end to piping welds and safe end in Volumetric and No branch piping welds Survace 84.2 B-G-1 Pressure retaining bolts and studs, in Volumetric No - Note 4 place i
84.3 B-G-1 Pressure retaining bolts and studs, when Volumetric and No - Note 4 removed Surface 84.4 B-G-1 Pressure retaining bolting Visual No - Note 4 B4.5 B-J Circumferential and longitudinal. pipe welds Volumetric No T' -B4.6 B-J Pipe branch connection welds exceeding Volumetric No L* 6" in diameter
-B4.7 B-J Pipe branch connection welds 6" and less Surface No l
!: -B4.8 B-J Socket welds Surface No I B4. 9 '- B-K-1 ' Integrally welded supports Volumetric .No l.
i . B4.10 - B-K-2 Support components, except hydraulic Visual No l snubbers B4.11 B-P- Exempted components Visual (IWA-5000)- No
'B4.12 B-G Pressure retaining bolting . Visual No l
L
---____-_J 1 -
O Table Table O Section XI O'1 ,
IWB-2600 IWB-2500 Item Examination Examination Relief No. Category Components and Parts to be Examined Method Requested Section 5. Pump Pressure Boundary and Pump Flywheels 85.1 B-G-1 Pressure retaining bolts and studs, in Volumetric No place B5.2 B-G-1 Pressure retaining bolts and studs, when Volumetric and No removed Surface 83.3 B-G-1 Pressure-retaining bolting Visual No B5.4 B-K-1 Integrally-welded supports Volumetric Yes - Note 8 B5.5 B-K-2 Support components (except hydraulic Visual No snubbers)
B5.6 B-L-1 Pump casing welds Volumetric Yes - Note 7 B5.7 B- L-2 Pump casings Visual No B5.8 B-P Exempted components Visual (IWA-5000) No Flywheels Volumetric No - Note 9 Section 6. Valve Pressure Boundary B6.1 B-G-1 Pressure retaining bolts and studs, in Volumetric Yes - Note 10 place 86.2 B-G-1 Pressure retaining bolts and studs, when Volumetric and Yes - Note 10 removed Surface B6. 3 B-G-1 Pressure-retaining bolting Visual No B6.4 B-K-1 Integrally-welded supports Volumetric No - Note 4 B6.5 B-K-2 Support components (except hydraulic Visual No snubbers)
_ - - = . - _ _ . . . - . .- -
~
r.
-Table Table Section ,- ;
.-IWB-2600. IWB-2500 XI Item' Examination Examination' Relief ,
No .- -Category ' Components and Parts to be Examined Method Requested B6.6 B-M-1 Valve body. welds Volumetric No - Note 4 '
'I B6. 7. - B-M-2 Valve bodies Visual No B6.8: B-PT Exempted components Visual.(IWA-5000) No .
.86.9 .B-G-2 . Pressure-retaining bolting Visual No 5
1
, w 4, ..
i
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s 6
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NOTES I
%./
- 1. There are limitations in access to weld SC-2 as shown on drawing E-NEU-661-005 caused by the reactor vessel supports. This inter-ference prevents volumetric examination of 19% of the weld, but does not constitute a variance from Code, as only.5% of this weld requires examination during the inspection interval. Sketch SK-M-97 shows this situation.
- 2. Weld SC-1, shown on drawing E-NEU-661-005 is partially inaccessible because of reactor vessel supports, which preclude 39% of the weld from being examined. As in Note 1, above,-this is in compliance with Code, as Table IWB-2500 requires that only 5% of the weld be examined. Sketches SK-M-97 and SK-M-228 show the Reactor Vessel Nozzle supports and adjacent areas.
p 3. The lower 50% of nozzles NS-2, NS-4, and NS-6 are inaccessible for
( volumetric examination of Category B-D Nozzle.to-shell welds.
These are the three nozzles that contain the integral Reactor Vessel support pads. ~Although some redesign of this area was-accomplished during construction to provide .for better .inspectabil-ity, we must still request a waiver on the Code requirements for 100% examination of all nozzles during the inspection interval. As an alternate to volumetric examination, these areas will be moni-tored for leaks and inspected visually for signs ofJstructural distress, until an inspection method meeting Code requirements'can be devised. Drawing E-NEU.-661-005 and sketches SK-M-97 and SK-M-228 show the arrangements in the nozzle area. Nozzles NS-1, NS-3 and NS-5 are accessible and code examinations will be performed.
- 4. There are no items of this category at Mi.11 stone Unit 2.
j
- 5. The Reactor Vessel supports at Millstone Unit.2'are integral with l "'
') three of the six nozzles and are excluded from this category by Table IWB-2500.
I-9
1
/ 6. NNECO requests a waiver on performing Code cladding examinations based upon the following:
- a) examinations of clad surfaces in the reactor vessel and reactor vessel head were attempted during the last refueling outage (December, 1977 to March, 1978) and were limited by access problems in the vessel and surface oxidation in the E
closure head.
11 b) the summer, 1976 addenda to Section XI deleted the requirements for these examinations.
3
^
F As an alternate, NNEC0 will perform visual examinations of cladding when the internal components are removed at the end of the interval to perform the Category B-N-3 inspections. Similar inspections
( will be made on steam generator and pressurizer cladding.
- 7. Since the pump casings are fabricated as cast stainless steel sections joined with austenitic welds, present volumetric techniques
~
and procedures are not applicable to in-service applications. As a 3 result, in-service examinations of the pumps, visual as well 'as volumetric, may be delayed until the tenth year as permitted by
/ Code. Should a volumetric technique be available at that time,
['
examinations shall be performed in accordance with the applicable item number. See drawing E-NEU-661-047.
~
- 8. Volumetric examinations of attachment welds is not possible because i of the cast stainless steel pump casing, as described above in Note 7. A surface examination will be utilized as an alternate.
{
See drawing E-NEU-661-047.
- , 9. Each reactor coolant pump flywheel shall be inspec~ted to the maximum extent practical as described below:
.j O I-10
- a. An in place ultrasonic volumetric examination of the areas of 9 higher stress concentration at the bore and keyway at approxi-mately 3-1/3 year intervals, during the refueling or maintenance shutdowns coinciding with the inservice inspection schedule as required by ASME Boiler and Pressure Vessel Code,Section XI.
- b. A complete ultrasonic examination of all exposed surfaces at approximately 10 year intervals, during the plant shutdown coinciding with the inservice inspection schedule required by the ASME Boiler and Pressure Vessel Code,Section XI. Removal of the flywheels is not required to perform these examinations.
- c. Examination procedure and acceptance criteria is in conformance with the requirements equivalent to those specified for Class I vessels in the ASME Boiler and Pressure Vessel Code,Section III -
Nuclear Power Plant Components. All flywheels shall be inspected by the same volumetric examination methods used during the baseline examination.
Limitations exist in the hub area where the closeness of the shaft support and s'eal prevents straight beam examinations of flywheel flat surfaces for 10" on top and 12" on the bottom radially out from the shaft. Examinations from the edge of the flywheel are possible and are currently being conducted.
- 10. In that the 2" diameter bonnet bolting in the safety injection system valves has spherical ends and cannot be volumetrically examined, the examination requirements for category B-G-2 will be applied.
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. .. MILLSTONE UNIT NO. 2-INSERVICE INSPECTION PROGRAM ;
l CLASS 2 COMPONENTS l The attached table provides a listing of Class 2 pressure-retaining components { (and their supports) which are subject to the inspection requirements of Sub-
; section IWC of Section XI of the ASME Boiler and Pressure Vessel Code,1974 Edition, and Addenda through Summer 1975.
These tabulations identify the components to be inspected, the components
- safety class, the applicable code to which the component was built, and the 1 nethod of examination. Relief from the inspection requirements of each Sub-l section is requested in cases where these inspection requirements have been l-determined to be impractical. Where relief is requested, specific information
- is provided which identifies the applicable code requirement, justification for the relief request, and the inspection method to be used as an alternative.
! The rules of IWA-4000 will be adhered to for repairs to all Class 2 components. l The inservice inspection and testing programs -outlined in the attached tabulation have been developed as a result of a design' review. - Should certain ASME Section XI Code requirements be .discoverea to be impractical due. to unforeseen reasons - during the process of. performing. inspections or tests,. relief will be requested ; from the specific Section XI Code requirement at .that time.-
~
Radiation levels in certain areas or of certain components:may be.found to pro .
- hibit the access for operators or inspectors to perform the inspections or tests L described in this program. _ If source strengths cannot be -reduced and access is
! still restricted by considerations of- compliance with the requirements of j Regulatory Guides 8.8 and 8.10, relief will be requested from 'the specific: Section XI Code requirements and alternative examination 'or test: requirements.- - be proposed. Ultrasonic examinations are required to be conducted.in' accordance with the pro-- l visions of Appendix I and Article 5 of Section V as required:by Paragraph IWA-2232. As an alternative to using Article 5 of Section.V,1NNECO proposes to use Appendix III of Section XI of. the 1974 Edition, Winter,1975, Addenda of the '
~
- - ASME Boiler and Pressure Vessel Code for ultrasonic Jexamination of piping systems.
It.is' recognized that Appendix III of Section'XI was issued-in the Winter,.1975, Addenda and, as such, has not been of ficially recognized by ~the NRC'by.ref-- erence in 10 CFR 50. However, Appendix III is the-first guideline that,has been published in the -ASME- Codes for the ultrasonic examination; of ; pipe welds,and.fas. such,:its use is essential.' Examinations of hydraulic snubbers will be conducted ~in'^accordance ,with Technical' -
. Specifications, Section 4.7.8.1 so :is excluded from Category C-E-2' in ' the ! <
accompanying table. :
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7 i 2 i MILLSTONE UNIT NO. 2
-INSERVICE INSPECTION PROGRAM--CLASS 2 CGtPONENTS ASME SECTION II-SUBSECTION IWC "S 75" ADDENDA Section XI I Item . Examination . Camponents and Parts Method of Code Relief
' Wo. Catemory To Be Examined Construction Code Area To Be Examined Examination Requested C1.1 - -C-A ' Steam Cenerators' ASME III. Class A - Shell and Head Welds, Volumetric-No - Note 1 ;
S 69 Addenda Tubesheet to Shell '
- Weld a C1.2, .C-Bf Nozzle 'to' Vessel Welds . Volumetric No C1.3- .C-C' Integrally Welded Surface No
. Supports !
LC1.4
-lC-D Bolting-Exceeding in Visual and No in Dia. . Either surface or Volumetric C1.1 - _C-A. - Shutdown Heat ASME III Class C Shell and Head Welds, Volumetric No Exchangers- S 69 Addenda including Tubesheet to Shell VW-2(a).of ASME VIII' . Welds
-:C1.2 2 C-B . Nozzle to Vessel Walds Surface Yes--Note 2 i
. .. C1.3 : C-C . Integrally Welded
' . Surface Not Applicable Supports Note 3 ,
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- or Volumetric l
' C2.1 C-C, _ Main Steam Piping B31.7 C1.2: Piping Welds Volumet'ric No
- C2.3 : .C-C. 4
_ Pipe ' Branch Connections Volumetric No II-2. - h.. s
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MILLSTOME UNIT NO. 2
; -INSERVICE INSPECTION PROGRAM-CLASS 2 CCHPcNENTS
. A9(E SECTION XI-SUBSECTION IWC "S 75" ATENDA ' .j i
~ ,
- t- _ . Section Il
'9, Item- R===ination Components and Parts Method Of Code Relief ~
_' No. Category -To Be Erasined Construction Code Area To Be Examined Examination Requested r , ' C2.5 .C-E-1 Safety Injection , Integ ra11y' M Jed Su rf ace No system (cont'd) Supports
'C2.6 . C-E - Support Components. Visual No ,
axcegg hydraglic snubbers ' C3.1. . . . . . ' C-F Low Pressure Safety . ASME Draft Code For Pump Casing W!ds Volumetric Not Applicaole Injection Pwsps ./ Pumps and Valves . Note 3 :)
, 1%8-Class II ,
, C3.2- C-D.' , Pressure Retalning Visual and No h.. .y 2 ' a Bolting > 1" either surfac<
r pg. O or volumetric q ' f 1V1. . -)- C3.3 - C-E-l'- , Integrally Wided Surface Not Applicable f' .n < Supports Note 3 2 -
, S . C3.4' C-E-2 * - '
,' Support Components' Visual No x;3, ) s, l. s-
'd( High Pressuye Safety . Pump Casing W lds
- C3.1 : C-F: ,
ASME:$ raft Code for Voltsm. tric .Not Applicable 'l Injection Pasaps - ' Pumps and Valves . Note 3 ,
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Bolting > 1" either surface or volumetric 7
~ HC3.3 C-E-11 Integrally Welded Surface Not Applicable Supports Note 3 ,
C3.4' C-E-2 -- Support Components Visual No j II-4
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3 l MILLSTONE UNIT NO. 2 , t INSERVICE INSPECTION PROGRAM-CLASS 2 COMPONENTS
. - ASME SECTION XI-SUBSECTION IWC "S 75" ADDENDA Section XI
- Itsa : Examination Components and Parts Method Of Code Relief Category To Be Exasined Construction Code Area To Be Examined Examination Requested
- No.
, ~
'C3.1- C-F Containment Spray Pump ASME Draf t Code For Pump Casing Wlds Volumetric Not Applicable i Pumps and Valves Note 3 1968-Class II Visual and C3.2 -C-D Pressure Retaining Not Applicable Bolting > 1" either surface Note 3 #
,: or volumetric I
C3.3? C-E-1 Integrally Welded Surface Not Applicable ' Supports Note 3 V ;C3.41 -C-E-2 Support components Visual No
'C4.1' C-F Valve s Various Valve Body Welds Volume tric Not Applicable Note 3 L C4. 2 ' . C-D Bolting > 1" Visual and No
- either surface 4
or volanetric
' C4.3 l ;C-E-1 Integrally E lded Surface Not Applicable Supports- Note 3 C4.4_. C-E-2 ~
Support Components- Surface' Not Applicable Note 3 N sII .
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- 1. Three of the five Category- C-A Steam Generator shell welds are presently included in the existing inservice inspection program. See Tech Specs.
Table 4.4-4.
- 2. Category C-B nozzle to' vessel welds in the shutdown he.it exchangers were originally inspected using liquid penetrant (surface examination). . The weld design precludes volumetric examination, as is required by Section XI.
Inservice examinations will be conducted using surface methods. See drawings 25203-20165 and 25203-20166. .
- 3. There are no items of this category.
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OPERATIONAL READINESS TESTING FOR PUMPS t There are twenty-five pumps at Millstone Unit 2 which qualify for operational 4 readiness testing under Subsection IWP of Section XI. Since all of these i pumps are either under continuous service or periodically surveillance tested , under the plant Technical Specifications, or other existing programs, the l !- additional data taking, formal evaluation of data and administration of records l and reports required by code will be implemented on April 26, 1979, at the j start of the next (second) inspection period. I l Table IWP lists the pumps falling under the program. test attributes and
'- frequency of testing.
The provisions of Subsection IWP will be adhered to insofar as installed j instrumentation allows at a test frequency compatible with Subsection IWP and j safe operating criteria. l IWA-2120 (c) requires that the Authorized Nuclear Inspector assure himself
- that inservice tests of pumps and valves have been completed and the results recorded. NNECO interprets this section of the code to mean that the ANI may elect to witness any or all operational readiness tests and the prepara-tions thereof. In that operating tests may be conducted at any hour, 'seven days a week, and that the ANI has no training or experience in plant operations, we request a waiver from IWA-2120 (c). As an alternate, NNECO and NUSCO Quality Assurance will witness, audit or otherwise verify that these tests
, are being properly conducted and documented. l' To meet the vibration monitoring requirements of ASME Section XI, Subsection j IWP, exception is taken to the specific vibration requirements of IWP and j an alternate, more effective vibration signature analysis program as described i herein, is proposed. During the inservice pump test, vibration data shall be acquired in the form of a " vibration signature" rather than a simple reading of overall vibration anplitude. The' vibration signature shall consist of a. plot of vibration velocity in units of inches per second, j versus f requency-in cycles per second, normally using ; a frequency range of. O i to 500 cycles per second. _ The vibration signature analysis approach provides - a more reliable means of detecting a deterioration of ptsap mechanical condition, a means of diagnosing the cause .of a problem and a more accurate assessment of vibration - severity. The. periodically acquired vibration signatures shall be
- compared _to a baseline reference signature and analyzed for changes in ampli-tude peaks exceeding a threshold value. Criteria for evaluation of, changes -
as to cause, severity and the establishment of the Alert and Required Action
~
j- Ranges shall be _ specified in the NNECO procedures. ' Vibration measurements are made typically with an accelerometer mounted a'ta. reference location on an equipment bearing housing and the output processed ~
- by a spectrum analyzer to produce a hard copy vibration signature. ,
i .. . -
- The measurement ' locations to be'used for monthly and baseline vibration
~ signature data shall be established and specified by NNECO procedures.~ -
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TABLE IWP FLOW SPEED INLET DIFFERENTIAL BEARING PUMP RESISTANCE CONTROL PRESSURE PRESSURE FLOW VIBRATION LUBRICATION TEMPERATURE FREQUENCY Service Water A Variable Fixed Sea Level X X X X Note 2 Monthly Service Water B Variable Fixed Sea Levtl X X X X Note 2 Monthly < _ Service Water C Variable Fixed Sea Level X X X X Note 2 Monthly
- Aux. Feedwater A . Fixed- Fixed X X X X Note 2 Monthly Aux. Feedwater B Fixed Fixed X X X X Note 2 Monthly T::rbine Driven Fixed Variable X X X X Note 2 Monthly Aux. Feedwater~ +
RBCCW'A : Variable Fixed X X X X X Note 2 Monthly RBCCW B Variable. Fixed X X X X X Note 2 Monthly RBCCW C Variable Fixed X X X X X Note 2 Monthly [ H P. Safety Injection A Fixed Fixed X X X X Note 2 Monthiy
' H.P. Safety Injection B. Fixed Fixed X X X X Note 2 Monthly H.B. Safety injection C Fixed' ' Fixed X X X X Note 2 Monthly L.P. Safety Injection A Fixed Fixed X X X X Note 2 Monthly
- L.P. Safety Injection B ' Fixed' Fixed X X X X Note 2 Monthly Containment Sphay A Fixed Fixed X X X X Note 2 Monthly Containment Spray B Fixed Fixed X X X X Note 2 Monthly Charging A Fixed. Fixed Note 1. X X X Note 2 Monthly Charging B Fixed Fixed Note 1 X X X Note 2 Monthly Charging C Fixed- Fixed Note I X X X Note 2 Monthly Spent Fuel A Fixed. Fixed -X X X X Note 2 Monthly Spent Fuel B Fixed Fixed X t X X Note 2 Monthly
^ Chilled Water A Fixed Fixed X X X X Note 2 Monthly Chilled Water B Fixed- Fixed X X X X Note 2 Monthly Boric Acid A.- Fixed Fixed ~X X X X Note 2 Monthly ;
- Boric Acid B Fixed Fixed X X X X Note 2 Monthly
. X = parameters to be meast. red or observed per Code
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v ., - ., NOTES TABLE IWP
- 1. Changing pumps are positive displacement pumps and will be tested during normal charging to the Reactor Coolant System. Under these conditions, flow measurement is indicative of pump performance.
- 2. Bearing Temperatures - None of the tabulated pumps have installed temper-ature sensors. The auxiliary feedwater, and HPSI pumps have bearing housings cooled by water which would prevent meaningful measurements on the housing. Boric acid, spent fuel pool cooling and containment spray have a single pump bearing in a large oil filled housing. The mass of.
the housing and its direct contact with the pumped liquid prevents meaningful measurements on this housing. The LPSI and chilled water pumps have _ shaf t bearings in the motor housing. Construction of,this housing and the influence of motor heat prevents meaningful temperature measurements on these bearings. The charging pump bearings are deeply recessed into the casing making valid temperature measurement unreliable. As an alternate to recording bearing temperatures, NNECO has elected to perform the vibration " signature". analysis described on page P-1 which should provide more meaningful data on the pump's mechanical characteristics than the Code referenced vibration and bearing temperature data. h t _I s g T'-' P-3 _ O
I i
~N OPERATIONAL READINESS TESTING FOR VALVES s/ There are approximately 250 valves at Millstone Unit 2 which qualify for operational readiness testing under Subsection IWV of Section XI, "S75" +
addenda. Some of these valves are presently being operated under sur-veillance testing required by the plant Technical Specifications, or in conjunction with pump surveillance, or during normal pump rotations. In addition, containment isolation valves are periodically leak-rate tested under the 10CFR50 Appendix J program. Table IWV-1, submitted herewith, identifies the valves to be tested, valve code classes, Section XI category as defined by IWV-2000, and test fre-quencies. Where exceptions to the Code are necessary due to design or operating considerations, they are so noted. The system boundary diagrams, included in this submittal, may be consulted to note the location of the valves. As with operational readiness testing of pumps, NNECO takes exception to IWA-2120(c) regarding the Authorized Nuclear Inspector's surveillance of operating tests. Valves with fail-safe actuators will be tested by observing the operation of these valves upon loss or simulated loss of actuator power. N f 4 )
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) ** . : * ' ., a 1 4 1 LEGEND FOR VALVE TESTING 1 i ' i j Q - Exercise valve (full stroke) for. operability every (3) months. 4 } LT - Valves are leak tested per Section XI Article IWV-3420. 2 j MT - Stroke time measurements are taken and compared to the stroke
- time limiting value per Section XI Article IWV-3410.
1 [ CV - Exercise check valves to the position required to fulfill their.' function every (3) months. l 2 SRV - Safety and relief valves are tested per Section XI Article IWV-3510. ET - Verify and record valve position before operations are performed and after operations are completed, and. verify that valve is locked or sealed. 7 CS - Exercise valve for operability every. cold shutdown.. RR - Exercise valve for operability every reactor refueling. P 1- , p I l e i ~ f 4
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25203-26126 SAFETY INJECTION SYSTEM Sh. 3 2-SI-007 2 E5 x .75 REL SRV 2-SI-008 2 E6 x 6 CK C CV 2-SI-009 2 C9 x 2 CK C CV 2-SI-010 2 E9 x 2 CK C CV 2-SI-011 2 C9 x 2 CK C CV 2-SI-012 2 J9 x 2 CK C CV 2-SI-ll3 2 H9 x 2 CK C CV 2-SI-ll4 2 H9 x 6 CK C CV x CS 2-SI-123 2 G9 x 2 CK C CV 2-SI-124 2 F9 x 6 CK C CV x CS 2-SI-133 2 D9 x 2 CK C CV 2-SI-134 2 D9 x 6 CK C CV x CS 2-SI-143 2 B9 x 2 CK C CV 2-SI-144 2 B9 x 6 CK C CV x CS 2-SI-211 2 Gil x 1 REL SRV 2-SI-215 1 Hll x x 12 CK C CV,LT 2-SI-217 1 H12 x ,x 12 CK C CV,LT x CS 2-SI-221 2 Kll x 1 REL SRV 2-SI-225 1 Fil x x 12 CK C CV,LT 2-SI-227 1 F12 x x 12 CK C CV,LT x CS 2-SI-231 2 Ell x 1 REL SRV 2-SI-235 1 D11 x x 12 CK C CV,LT 2-SI-237 1 D12 x x 12 CK C CV,LT x CS 2-SI-241 2 C11 x 1 REL SRV 2- SI-245 1 Bil x x 12 CK C CV,LT 2- SI-247 1 B12 x x 12 CK C CV,LT x CS 2- SI-306 2 F5 x 10 Ball AO LO ET 2- SI-401 2 C1 x 8 CK C CV 2- SI-405 2 D4 x 3 CK C CV V-3
m w ' c a @ n 3 t . ,2 . E 3 E $ 3 .5 sg 5 1 8 8 T % 4* Valve [ Valve l e gc Category $ 3 5 h gj g gq og Number o m A B C D E $ $ M E $ $ $ $$ 25203-26126 SAFETY INJECTION SYSTEM Sh. 3 2-SI-409 2 C7 x .75 REL SRV 8 CK C CV 2-SI-410 2 F1 x 2-SI-414 2 E4 x 3 CK C CV 1 REL SRV 2-SI-417 2 G8 x 2-SI-427 2 F4 x 3 CK C CV 2-SI-434 2 G3 x 10 CK C CV x CS 2-SI-439 2 C7 x .75 REL SRV 2-SI-446 2 H3 x 10 CK C CV x CS J12 REL SRV 2-SI-466 2 x 1.5 2-SI-468 2 F7 x 1.5 REL SRV 2-SI-469 1 D7 x 1 REL SRV 2-SI-614 1 H11 x 12 GA MO LO ET 2-SI-615 2 H9 x x 6 GL M0 C Q HT,LT 2-SI-616 2 H8 x 2 GL Mo C Q
- MT 2-SI-617 2 J8 x 2 GL M0 C Q MT 2-SI-618 1 H12 x x 1 GL A0 C Q MT,LT 2-SI-624 1 Fil x 12 GA M0 LO ET 2-SI-625 2 F9 x x 6 GL M0 C Q MT,LT 2-SI-626 2 F8 x 2 GL M0 C Q MT 2-SI-627 2 G8 x 2 GL M0 C Q MT 2-SI-628 1 F12 x x 1 GL A0 C Q MT,LT V-4
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valv. j 85 Category 3 o a g g, a. $q g gg Nder u M A B C D E $ $ M $ $ $ $$ ,, 25203-26126 SAFETY INJECTION SYSTEM Sh. 3 2-SI-660 2 K4 x 4 GL A0 0 Q x CS MT 2-SI-706A 1 H10 x 6 CK C CV 2-SI-706B 1 F10 ,x 6 CK C CV 2-SI-706C 1 D10 i x 6 CK C CV 2-SI-706D 1 B10 x 6 CK C CV 2-SI-312 2 D9 x .75 GL A0 0 Q MT 2-SI-422 2 x 2" CK C CV 2-SI-424 2 x 2" CK C CV 2-SI-426 2 x 2" CK C CV 2-SI-448 2 x 2" CK C CV 2-SI-451 2 x 2" CK C CV 9 V-6
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ag Nder h" j A B C 'D E $ $ 5 $ $ CONTAINMENT SPRAY SYSTEM Sh. 3 2-CS-2A 2 K3 x 8" CK C CV x RR 2-CS-2B 2 J3 x 8" CK C CV x RR 2-CS-4.1A 2 K8 x 8" GA M0 C Q
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2-CS-4.1B 2 J8 x 8" CA M0 C Q MT 2-CS-SA 2 K8 x 8" CK' C CV x RR 2-CS-5B 2 J8 x 8" CK C CV x RR 2-CS-13.1A 2 B3 x 18" GA M0 LO Q x CS MT 2-CS-13.lB 2 B3 x 18" GA M0 LO Q x CS - MT 2-CS-14A 2 B3 x 18 CK C CV 2-CS-14B 2 B3 x 18 CK C CV 2-CS-15A 2 B4 x 24 CK C CV 2-CS-15B 2 B4 x 24 CK C CV 2-CS-16.1A 2 B4 x 24 GA M0 C Q MT 2-CS-16.1B 2 B4 x 24 GA M0 C Q MT 2-CS-6A 2 x 2" CK C CV 2-CS-6B 2 x 2" CK C CV V-7 .
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- I s RELIEF REQUEST BASIS i
SYSTEM: SAFETY INJECTION Valve: 2-SI-114 Category: C Class: 2 Function: Prevent backflow in low pressure safety injection a line. Test Requirement: Exercise to open position every three months. Basis for Relief: Low pressure safety injection pump does not generate sufficient pressure to overcome safety injection tank pressure downstream of valve. , Alternate Testing: Exercise to open position during cold shutdown when
~
Safety Injection Tank is isolated and Reactor Coolant System pressure is less than 180 PSIG. - 1 Valve: 2-SI-124 .
, Category: C i Class: 2 Function: Prevent backflow in low pressure safety injection line.
Test Requirement: Exercise to open position every three months.
- Basis for Relief
- Low pressure safety injection' pump 'does not generate j aufficient pressure to overcome safety injection tank pressure downstream of valve.
1 Alternate Testing: Exercise'to.open position during cold shutdown when Safety Injection Tank is isolated and Reactor Coolant System pressure is less than 180 PSIG. ( Valve: '2-SI-134 Category: C Class: 2
. Function: Prevent. backflow;in low pressure safety injection line.
-Test: Requirement: Exercise to open position every three months.-
p. Basis for Relief: Low-pressure safety injection pump does not generate 1
.I sufficient pressure to overcome safetyLinjection tank ' \s -) pressure downstream of valve.
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n Alternate Testing: Exercise to open position during cold shutdown when ( Safety Injection Tank is isolated and Reactor Coolant System pressure is less than 180 PSIC. Valve: 2-SI-144 Category: C Class: 2 Function: Prevent backflow in low pressure safety injection line. Test Requirement: Exercise to open position every three months. Basis for Relief: Low pressure safety injection pump does not generate sufficient pressure'to overcome safety injection tank pressure downstream of valve. Alternate Testing: Exercise to open position during cold shutdown when Safety Injection Tank is isolated and Reactor Coolant System pressure is less than 180 PSIG. 1 Valve: 2-S'I-217 Category: A-C Class: 1 Function: Provide isolation and backflow prevention between-Reactor Coolant System and Safety Injection Tank No. 1. Test Requirement: Exercise check valve to open position quarterly. Basis for Relief: Because of pressure differential across disc this: valve cannot be opened with the Reactor Coolant System at normal operating pressure.~ Alternate Testing: Exercise valve for operability _during cold shutdown when Reactor Coolant. System is less than 180 PSIG.- Valve: 2-SI-227 Category: A-C Class: 1 a Function: Provide isolation and backflow prevention between; Reactor Coolant' System and S'afety Injection Tank No. 2. w
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1 Test Requirement: Exercise check valve to open position quarterly. Basis for Relief: Because of pressure differential across disc this valve cannot be opened with the Reactor Coolant System at normal operating pressure. Alternate Testing: Exercise valve for operability during cold shutdown when Reactor Coolant System pressure is less than 180 PSIG. Valve: 2-SI-237 Category: A-C Class: 1 Function: Provide isolation and backflow prevention between Reactor Coolant System and Safety Injection' Tank' No. 3. Test Requirement: Exercise-check valve to open position quarterly. Basis for Relief: Because of pressure differential across disc this valve cannot be opened with the Reactar Coolant System at normal operating pressure. . Alternate Testing: Exercise valve for operability'during cold shutdown-when coolant system pressure is less than 180 PSIC. Valve: 2-SI-247. Category: .A-C Class: 1 Function: Provide isolation and backflow prevention between-
. Reactor Coolant System ~and Safety Injection Tank
'No. 4.
Test Requirement: Exercise check valve to'open position q'uarterly. Basis for Relief: Because of pressure differential across disc this
' valve.cannot be opened with the Reactor" Coolant. System at-normal operational pressure.-
Alternate Testing: Exercise. valve for-operability during cold shutdown
=when' coolant system l pressure:is less than:180 PSIC.
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Valve: 2-SI-434 ' Category: C I Class: 2 r Function: Prevent backflow through low pressure safety injection pump. Test Requisement: Exercise to open position every three months. Basis for Relief: This valve cannot be exercised without placing the low pressure safety injection system in an inoperative status by opening locked closed valve 2-SI-657. Alternate Testing: Exercise to open position during cold shutdown. ; Valve: 2-SI-446 Category: C Class: 2 ; Function: Prevent backflow through low pressure safety injection pump. . Test Requirement: Exercise to open position'every th'ree months.
' f Basis for Relief: This valve cannot.be exercised without placing the-low pressure safety injection system in an inoperative.
status by opening locked closed valve 2-SI-657. Alternate Testing: ' Exercise to open position,during cold shutdown. ! k s
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Valve: 2-SI-651 Category: B Class: 1 Function: Isolate shutdown cooling system piping from Reactor Coolant System. Test Requirement: Exercise and measure stroke time every three months. Basis for Relief: Valves are locked closed when Reactor Coolant System pressure exceeds 300 PSIG to protect the low pressure shutdown piping. Valve exercise would require viola-tion of-plant interlocks. Alternate Testing: Exercise and measure stroke time during cold shutdown when Reactor Coolant System pressure is less than 300 PSIC. . Valve: 2-SI-652 Category: B Class: 1 Function: Isolate shutdown cooling system piping from Reactor ' Coolant System.
'5 g Test Requirement: Exercise and measure stroke time every three months.
Basis for Relief: Valves are locked closed when Reactor Coolant System- " pressure exceeds 300 PSIC to protect the low pressure shutdown cooling piping. _ Valve exercise would require. violation of plant interlocks. Alternate Testing: Exercise and measure stroke time during cold shutdown when Reactor. Coolant System pressure is.less-than 300 PSIG. Valve: 2-SI-659 Category: B Class: 2 Function: Isolate _ minimum.flowrecirculationpihingfrom-refueling water storage t'ank when Safety: Injection System is operating in containment sump'recircula-tion mode. Test Requirement:~ Exerc'ise'(full stroke) and measure stroke-time every three months. Basis-for' Relief: . Valve is required by plant technical specification.
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. plant operation. ;
h Alternate Testing: _ Exercise _(full stroke):and~ measure: stroke time during'- shutdown..
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i ~ .: .., Valve: 2-SI-660 Category: B Class: 2 Function: Isolate minimum flow recirculation piping from refueling water storage tank when Safety Injection System is operating in containment sump recirculation mode. Test Requirement: Exercise _(full stroke) and measure stroke time every three months. Basis for Relief: Valve is required by plant technical specification to be open with valve operator power removed during plant operation. Alternate Testing: Exercisc-(full stroke) and measure stroke time during -I cold shutdown. Valve: 2-CS-2A Category: C Class: 2 Function: Prevent backflow through Containment Spray Pump. Test Requirement: Exercise to open position every three months. 1 Basis for Relief: This valve cannot be exercised without placing the containment spray system in an inoperative status in violation of Technical Specification requirements. Alternate Testing: Exercise to open position during reactor refueling. Valve: 2-CS-2B Category: C Class: 2 Function: Prevent backflow through Containment Spray Pump. Test Requirement: Exercise to'open position everylthree months. Basis for Relief: This valve cannot be exercised without placing the' containment spray system in an inoperative status. in violation of Technical Specification requirements.
- Alternate Testing: . Exercise to open position _during reactor refueling.
Valve: 2-CS-5A Category: C' Class: 2
\
Function: _f - Provide post incident containment isolat' ion ~inside containment.- _ V . a -
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{. Test Requirement: Exercise to open position every three months. .I
. Basis for Relief: Testing of valve would require containment spray f
- system be made inoperable. Both systems are required' '
j' by Technical Specification to be operable during ; j plant operation. 1
- Alternate Testing
- Exercise. valve to open position with air during reactor refueling. ;
l j. l Valve: 2-CS-5B l Category: C ,
- Class
- 2 l
j Function: Provide post incident containment isolatio'n inside j containment. 1 l Test Requirement: Exercise to open position every three months. a ! Basis for Relief: Testing of valve' would require containment spray _. system ! be made inoperable. Both systems are required by 1 Technical Specification to be operable during plant. operation. E' l Alternate Testing: Exercise valve to open position with air during . 7 reactor refueling.. . - F l~ o 1 1 i
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i Valve: 2-CS-13.lA Category: B Class: 2 0 , l 4 Function: Reftieling Water Storage Tank' Outlet Header "A" Isolation Valve. Test Requirement: Exercise valve for operability every three months. ; i Basis for Relief: Failure of this-valve in closed position would interrupt i an emergency core cooling flowpath. i Alternate Testing: This valve vill be exercised _for operability during
- cold shutdown.
4 l Valve: 2-CS-13.lB l Category: B r Class: 2 j Function: Refueling Water Storage Tank Outlet' Header "B" Isolation. ! 3 Valve. Test Requirement: Exercise valve for operability every-three months. Basis for Relief: Failure of this valve in closed position would interrupt 4 an emergency core cooling flowpath. Alternate Testing: This valve will be exercised for operability during, j- - cold shutdown. 1 1 4
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- 9 RELIEF REQUEST BASIS ,
O ' Valve: 2-CH-515 ; Category: B Class: 2 Function: Isointe Reactor Coolant System letdown lire on safety injection actuation signal. Test Requirement: Exercise (full stroke) and measure stroke time every three monthe. Basis for Relief: Operation of this valve during plant operation would cause undes'. rabic thermal transients on the regenerative heat exchanger. This component has a limited number of design - thermal transients. Alternate Testing: Exercise (full stroke) and measure stroke time during cold shutdown. Valve: 2-CH-516 Category: B Class: 2 Function: Isolate Reactor Coolant System letdown line on containment isolation signal. Test Requirement: Exercise (full stroke) and measure stroke time every - three months. Basis for Relief: Operation of this valve during plant operation would. cause undesirable thermal transients on the regenerative-
-heat exchanger. This component has a limited number of design thermal transients.'
Alternate Testing: Exercise .(full stroke) and measure stroke- time during cold shutdown. Valve: 2-CH-089' Category: 'B Class: 2 Function: Provide containment isolation for RCS letdown piping on containment isolation. signal.: Test Requirement: (1) Exercise (full stroke) and measure stroke time every three months.-
~
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= . _ . _ _ _ _ _ _ . . _ _ _ _ _ _ . _ _ . _ _ _ _ . . . , _ _ _ . . _ . . . , _ _ _ _ . _ _ .
l . ! Basis for Reliefs (1) Operation of this valve during plant operation } would cause undesirable thermal transients on the
- regenerative heat exchanger. This component has a j limited number of design thermal transients.
! Alternate Testing: (1) Exercise (full stroke) and measure stroke time ! during cold shutdowns. t Valve: 2-CH-501 } Category: B i Class: 2 4 Function: Isolate volume control tank from charging pump suction . upon Safety Injection Actuation Signal. j
'i I Test Requirement: Exercise full stroke and measure stroke time every-
. three months. 4
. i j Basis for Relief: Exercising this valve would require interruption of charging flow with the~ attendant, undesirable, thermal ,
- ' transient on the regenerative heat exchanger. If an-alternate charging pump suction source were utilized ;
l an undesirable Reactor. Coolant-System boron concentra-tion transient could result.. i Alternate Testing: Exercise full stroke and measure stroke time during
~
cold shutdown. c i f - 1 i I . i ' A l 4 4 - 'V
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N d er u S A B C D E $ $ M $ $ 25203-26126 FEEDWATER SYSTEM Sh. 4 2- W-5A 2 ES 'x x 18 STOP- AO O Q x CS CK MT CV 2-W-5B 2 E2 x x 18 STOP- A0 0 Q x CS CK MT CV 2- W-7 3 C5 x 6 CK C CV x CS 2-W-8A 3 B5 x 4 CK C CV x CS 2- W-8B 3 B5 x 4* CK C CV x CS 2-W-12A 2 E6 x x 6 STOP- A0 C Q x CS CK MT CV 2-W-12B 2 E2 x x 6 STOP- A0 C Q x CS CK MT CV 2- W-32A 3 C5 x 1.5 CK C CV 2-W-32B 3 B5 x 1.5 CK C CV 2- W-33 3 C5 x 1.5 CK C CV 2-W-43A 3 D6 x 4 GL MO O Q MT 2-W-43B 3 D2 x 4" GL MO O Q MT 2-W-44 3 C6 x 6" GA M0 C Q MT 2- W-56A 3 D6 x 6" GA H C Q 2- W-56B 3 D1 x
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4 i RELIEF REQUEST BASIS Valve: 2-FW-5A-3 Category: BC 4 Class: 2 Function: Prevent backflow in main feedline to No. I steam i generator. I e
, Test Requirement: Exercise (full stroke) for operability every three j mort,hs. Take stroke time measurements per IWV-3410.
Basis for Relief: Valv'e exercise during plant operation would result insloss of feedwater flow. 1 t j Alternate Testing: Exercise valve for operability and measure stroke * [ ' time during cold shutdown. 1 4 Valve: 2-FW-5B Category: BC Class: 2 1 Function: Prevent backflow in main feedline to No. 2 steam il generator. ! N I
- Test Requirement: Exercise (full stroke) for operability every three months. .Take stroke time measurements per IWV-3410.
l Basis for Relief: Valve exercise'dur'ing plant operation would result in loss of feedwater flow. Alternate Testing: Exercise valve for operability and measure' stroke time during cold shutdown. Valve: 2-FW-12A
, Category: BC Class: 2 l-Function: Prevent backflow in auxiliary feedwater line to No.-1 steam. generator.
i
' Test Requirement: Exercise (full stroke) for operability every three months. Take' stroke time measurements per IWV-3410..
4 Basis for Relief: Valve operator exercise, without auxiliary feed-system. ~ flow will not result in actual valve exercise. i Initiating
! auxiliary'feedwater1 flow during plant operation c'ould result in feed flow anomalies.
'~ T- Alternate Testing: Exercise. valve for operability and measure' stroke time s ,/ during cold shutdown. .
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1. i Valve: 2-FW-12B
) Category:
Class: BC 2 Function: Prevent' backflow in auxiliary feedwater line to j No. 2 Steau Generator. 4- Test Requirement: Exercise (full, stroke) for operability every three
- months. Take~ stroke ~ time measurements per IWV-3410.
Basis for Relief: Valve operator exercise, without auxiliary feed system
- flow will not result in actual valve exercise. Initiating
~
i auxiliary-~feedwater flow during plant operation could ! result in feed flow anomalies. 1-Alternate Testing: Exercise valve for operability and measure stroke time during cold sh'utdowns. I i Valve: 2-W-7 o Category: C Class: 3 Function: Prevent backflow through. steam driven auxiliary feed j pump during operation of other auxiliary feed pumps. I
\ Test. Requirement: Exercise quarterly for operability.
k Basis for Relief: Operation of this valve would require establishing flow.- L .through the auxiliary feed lines to the steam generator. Introduction of this cold. water could result in steam l-generator level . instability.and/or undesirable thermal i '- transients to the' feed nozzles. l e - Alternate Testing: Exercise valve for operability during cold shutdown. m y
's Valve: s 2-FW-8A- '--
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1 Category: L C $, ^ Class:
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' Function: '
-Prevent backflow through motor. driven'auxiliaryifeed-
. pump during operation'of other auxiliary feed' pumps.=.
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1: Test Requirement: Exercise quarterly for operability.' 4 q v4 ( Basis for 3elief:' Operation of th'is-valve:would require establishing; i ~,' ' flow throughtthe auxiliary.fced; lines to the' steam generator. ,. fatroduction of3this cold water could '
. result .in steam ge nerator ' level; instability and/or '
. undesiipble : thert::ll trannient,s ; to . the . feed ' nozzles. ?
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T Alternate Testing: Exercise valve for operability during cold shutdown. Valve: 2-FW-8B Category: C Class: 3 Function: Prevent backflow through motor driven auxiliary feed pump during operation of other auxiliary feed pumps. Test Requirement: Exercise quarterly for operability. Basis for Relief: Operation of this valve would require establishing flow through the auxiliary feed lines to.the steam generator. . Introduction of this cold water could result in steam generator level instability and/or undesirable thermal transients to the feed nozzles. Alternate Testing: Exercise valve for operability during cold shutdown. V-24
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25203-26126 MAIN STEAM Sh. 2 2-MS-4A 3 D-4 x 4" CK C CV 2-MS-4B 3 C-4 x 4" CK C CV 2-MS-64A 2 E-4 x 34" STOP A0 0 Q x CS MT 2-MS-64B 2 B-5 x ! 34" STOP A0 0 Q x CS MT 2-MS-65A 2 D-4 x 3" GL. M0 C Q x CS Mr 2-MS-65B 2 B-5 x 3" GL M0 C Q x CS MT 2-MS-190A 2 D-3 x 8" GL A0 C Q x CS MT 2-MS-190B 2 C-3 x 8" GL A0 C Q x CS MT 2-MS-201 2 D-3 x 4" GA M0 C Q MT 2-MS-202 2 C-3 x - 4" GA M0 C Q MT 2-MS-191A 2 C-1 x .5 GL A0 Q MT 2-MS-191B 2 B-1 x .5 GL A0 Q MT 2-MS-220A 2 D-1 x 2" GL A0 Q MT 2-MS-220B 2 B-1 x 2" GL A0 Q MT V-29
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RELIEF REQUEST BASIS
,, s .
System: Main Steam
- 1. Valve: 2-MS-64A Category: B-C Class: 2
- Function: Stop flow from steam generator No. 1 following-t steam line rupture downstream of valve.
Test Requirement: Exercise valve for operability and measure- ! stroke time every three months. Basis for Relief: Full stroke testing of this valve would require-plant shutdown. Alternate Testing: Part-stroke exercise every three months and full stroke exercise and measure stroke during cold j shutdown.
- 2. Valve: 2-MS-64B Category: B-C ~i Class: 2
- ( Function: Stop flow from steam generator No. 2 following steam line rupture downstream of valve.
Test Requirement: Exercise valve for operability ~and measure
- stroke time every three months.
1 Basis'for Relief: Full stroke testing of this valve would require
- plant shutdown.
Alternate Testing: Part-stroke exercise =every three months and full stroke exercise and measure stroke time during cold shutdown.
- 3. Valve: 2-MS-65A-Category: .B i Class: 2.
Function: Startup bypass valve around main steam isolation valve for No. 1 steam generator. l Test Requirement: : Exercise. valve (full stroke) for' operability, l . and stroke time.every three months.. L: __ - m 1 sy_31' h, , . , , . . . . ,. -
- - . , , - . . . .- i ~ - .
l Basis for Relief: Valve is normally closed and not required to change position during plant operation. Failure O of this valve in the open position during exercise would jeopardize the ability to stop steam flow in the event of downstream rupture. Alternate Testing: Full stroke exercise and measure stroke time during cold shutdown.. 4 Valve: 2-MS-65B Category: B Class: 2 Function: Start-up bypass valve around main steam isolation valve for No. 2 steam generator. Test Requirement: Exercise valve (full stroke) for operability and stroke time every three months. Basis for Relief: Valve is normally closed and not required to change position during plant operation. Failure of this valve in the open position during exercise would jeopardize the ability to stop steam flow in the event of a downstream rupture. Alternate Testing: Full stroke exercise and measure stroke time O during cold shutdown.
- 5. Relief Request Basis:
Valve: 2-MS-190A Category: B Class: 2 Function: Provide control of steah flow from No. 1 steam generator to atmosphere during cooldown. Test Requirement: Exercise (full stroke) for operability and measure stroke time every three months. Basis for Relief: Operation of valve during plant operation could result in steam flow transient. Isolation of this valve to allow exercising during operation could reduce plant ability to withstand a turbine trip transient. Alternate Testing: Full stroke exercise and measure stroke
- time during cold shutdown.
O V-32
l
- 6. Valve: 2-MS-190B-i Category: B Class: 2 l l
$- Function: Provide control of steam flow from No. 2 steam generator.to atmosphere during cooldown. l l Test Requirement: Exercise (full stroke) for operability and ). measure _ stroke time every three months. Basis for-Relief: . Operation of valve during plant operation . [ could result in steam flow transient. Isola-tion of.this valve to allow exercising during.
- . operation could reduce plant ability to withstand I a turbine trip transient. ,
4 F l-' Alternate Testing: Full stroke exercise and measure stroke time during cold shutdown. ; i, f f. 7
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4 4 3 A es 25203-26126 CIIILLED WATER SYSTEM Sh. 10 - .-_ 2-CIN-1 3 B6 x 2 CK C CV 2-CIN-31 3 B4 x 2 CK C CV 2-C11W-3 3 C5 x 1.5 GL A0 C Q I E 2-CIN-33 3 C3- x 1.5 GL A0 0 Q MT 2-CIN-11 3 C5 x 1.5 GL' A0 0 Q MT 2-CIN-12 3 C4 x 1.5 GL A0 0 Q MT ~ 2-CIN-13 3 D5 x 1.5 GL AO O Q MT 2-C11W-14 3 D4 x 1.5 GL AO O Q m 2-CIN-4 3 D6 x 1.5 3-Way A0 Q MT 2-CHW-34 3 D3 x 1.5 3-way A0 Q MT S V-34 -
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g UE mm CONTAINMENT ISOLATION VALVES (Close on CIAS) 0 Containment Air Sample 2-AC-12 2 x 1" BFLY A0 Q MT 0 Containment Air Sample 2-AC-15 2 x 1" BFLY A0 Q MT 1" BFLY A0 0 Q Containment Air Sample 2-AC-20 2 x l MT 1" A0 0 Q Containment Air Sample 2-AC-47 2 x BFLY, MT 1.5 BFLY A0 0 Q Containment Air Sample 2-EB-88 2 x MT 0 Containment Air St.mple 2-EB-89 2 x 1.5 BFLY A0 Q MT
.75 GL A0 0 Q x CS Reactor Coolant Pump Seal 2-CH-506 2 x MT Leak-Off
.75 GL A0 0 x CS Reactor Coolant Pump Seal 2-CH-198 2 x Q MT Leak-Off 3 GL A0 0 Q Waste Gas Header 2-CR-ll.1 2 x .
MT 3 GL A0 0 Q Waste Gas Header 2-GR-ll.2 2 x MT V-35
4 M 1 RELIEF REQUEST BASIS Valve: 2-CH-506 Category: B Class: 2 Function: Isolate Reactor Coolant Pump seal leakoff line at containment penetration. Test Requirement: Exercise and measure stroke time every three months. } Basis for Relief: Exercise of this valve would secure reactor coolant pump seal controlled bleed off and could result in seal degradation. Alternate Testing: Exercise and measure stroke-time during cold shutdown when reactor coolant pumps are secured. f i Valve: 2-CH-198 Category: B Class: 2 Function: Isolate Reactor Coolant Pump seal leakoff line at , containment penetration. Test Requirement: Exercise and measure stroke time every three months. t Basis for Relief: Exercise of this valve would secure reactor coolant pump seal controlled bleed off and could result in seal degradation. Alternate Testing: Exercise and measure stroke time during cold shutdown . When reactor coolant pumps are secured. b 4 i h
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SYSTEM PRESSURE TESTS Articles IWA-5000, IWB-5000, IWC-5000 and IWD-5000 discuss the requirements cf system pressure tests for Classes 1, 2 and 3 components. Table BCD-5000 presents the system pressure test requirements for the Hillstone Unit 2 components and notes departures from Code where it was deemed necessary. Test requirements for open-ended lines such as suction lines from storage tanks, and which receive static tests, are not addressed in the table. In that NNECO and NUSCO Quality Assurance personnel will be witnessing these tests or auditing the test results, exception to IWA-2120, concerning the Authorized Nuclear Inspector, will be taken. The location of check valves in several systems that penetrate the primary containment preclude the Class 1 pressure test boundary from extending out-ward beyond the first of such valves, usually located inside containment even though the Class change boundary is outside containment. In these cases, the Class 1 leakage and pressure test Mundary would be the inside check valve. Conversely, pressure tests of Class 2 systems, which are out-side containment, would have to be bounded at a stop valve which may or may
- not be the Class 1/ Class 2 boundary.
Precautions must be taken in view of the dif ferences that exist in Class 1/ bh Class 2 test pressures to prevent overpressurization of the Class 1 components. k As an alternate to the Summer,1975 Addendum, NNECO proposes to utilize the rules of the Winter,1977 Addendum, IWA-5213, to define test condition holding time for all pressure tests. In systems which contain pumps, it will not be possible to utilize the pump casing as the boundary between high pressure and low pressure tests without overpressurizing suction piping during the high pressure test. In these cases, the discharge isolation valve will be considered the test boundary, f J t v> ,
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l - ! , . TABLE BCD - 5000 SYSTDi PRESSURE TESTS
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g TEST CODE TEST SYSTDt PRESSURE PRESSURE REMARKS (Psig) (psig) Class 1 (IWB-5000) Reactor Coolant Pressure Boundary a System Leakage Test 2250 2250 In compliance with Code System Hydrostatic Test 2430 @ 2430 @ In Compliance with 200F 200F Code 4 Class 2 (IWC-5000) HPSI 1125 1125 In Compliance with Code-(IWC-5220c) Containment Spray 254 254 In Compliance with Code (IWC-5220c) LPSI/ Shutdown Cooling Pump suction piping from 375 375 In compliance with 4 2-SI-651 to 2-SI-432 and Code j 2-SI-444. 1 1 Pump discharge piping 625 625 In Compliance with
! Code i Main Steam 1250 1250 In Compliance with from SG's to 2-MS-64A/B Code 2-MS-65A/B, and . 2-MS-201 -
and 2-MS-202. Feedwater from 2-FW-5A/B and 1250 1250 In Compliance with-2-FW-12A/B to SG's , Code CVCS Boric Acid subsysten - 188 188 In Compliance with h Code ! Charging pump suction 188 188 In Compliance with header ' Code . a f PT-2
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, MILLSTONE UNIT NO. 2 SYSTEM PRESSURE TESTS (cont'd)
TEST CODE TEST SYSTDi PRESSURE PRESSURE RDfARKS (psig) (psig) Charging pump discharge 3419 3419 In Compliance with header Code Letdown from RCS, Valve 3106 3106 In Compliance with 2-CH-516 to RHX to Code 2-CH-89 Class 3 (IWD-5000) Spent Fuel Pool Cooling. Pump Suction piping 55 55 In Compliance with Code Pump Discharge piping 110 110 In Compliance with Code Auxiliary Feedwater Aux. Feedpump suction
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55 55 In Compliance with piping Code Aux. Feedpump discharge 1760 1760 In Compliance with piping to 2-FW-43A/B ' Code Aux. Feedpump discharge 1210 1210 In Compliance with piping from 2-FW-43A/B Code to 2-FW-12A/B RBCCW 165 165 In Compliance with Code l Service Water Cast Iron underground 94 _94 ' .In Compliance with
-Code t
Relief Valve inlet piping 188 94 See Note 1-4 Remaining system piping 110 94 See Note 1= Chilled Water 55 55 In Compliance.with - Code , Main Steam-( from valves 2-MS-201 and' 1100 -1100 In' Compliance with-
~ 2-MS-202 to SG Aux. Feedpump- ,. Code.
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QA L ~, , NOTES
- 1. The service water system consists of piping and components designed to three different pressures, depending upon service conditions and material selection:
Cast Iron Underground Po = 85 psig [ Relief Valve Inlets Po = 150 psig Balance (majority) of system Pp = 100 psig In most instances, it is not possible to isolate these sections from each other to permit Code pressure tests. NNECO requests a waiver from the requirements of IWD-5200 (a) for the service water system for the two
. higher pressure sections, and as an alternate, propose to test the entire service water system to 94 psig, test pressure, based on the underground -
portion. Although this pressure is lower than the design pressure for
- most of the service water system, it is approximately 131 times the system operating pressure and would constitute a meaningful hydrostatic test.
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