ML18064A810
| ML18064A810 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/18/1995 |
| From: | Gamberoni M NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9506280527 | |
| Download: ML18064A810 (42) | |
Text
I i
/
~..
(
I
.. r:.
- .~:*
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 18, 1995 LICENSEE:
Consumers Power Company FACILITY:
Palisades Nuclear Plant
SUBJECT:
PALISADES REACTOR VESSEL ANNEALING MEETING
SUMMARY
A meeting was held at NRC Headquarters on June 6, 1995, between Consumers Power Company and the NRC to discuss the Palisades reactor vessel annealing.
This was the first working level meeting between the staff and the Palisades Annealing Team.
During the meeting, Palisades provided an overview of its annealing plan.
In addition, the schedule and content of Palisades' application was discussed.
A list of attendees is provided as Attachment I. Attachments 2 and 3 are the handout and slides presented at the meeting, respectively. Attachment 4 is a schedule of upcoming meetings related to the Palisades annealing and the Marble Hill demonstration project.
BACKGROUND The staff issued a safety evaluation (Sf} on April. 12, 1995, for the Palisades plant which concluded that the margins of safety intended by the pressurized thermal shock (PTS} rule will be satisfied through the 14th refueling outage, scheduled for late 1999.
In accordance with 10 CFR 50.61, 3 years pri~r to exceeding the screening criteria the licensee shall submit a plant~specific analysis to determine if operation beyond the screening criteria is acceptable.
As stated in the April 12 SE, submission of an annealing plan will be an acceptable alternative to a plant-specific_ analysis.
PRESENTATION/DISCUSSION Consumers Power began its presentation by reviewing the overall schedule of its annealing project. The contract to anneal the reactor vessel was awarded to Westinghouse.
Consumers plans a four-phase project: Phase (I} conceptual design, Phase (II} detailed design, Phase (Ill}.construction, and Phase (IV}
implementation.
The timeframes associated with the phases are provided in.
Consumers plans on submitting an Application for Approval for Thermal Annealing (AFATA} at the end of Phase I, scheduled for October I, 1995; select portions of the application may be submitted earlier as available.
Consumers is requesting NRC approval of the AFATA by June 1, 1996, to support authorization for the construction phase scheduled to begin October 1996.
Currently, Consumers has only been authorized by its senior management to proceed with Phase I. The staff questioned the existing schedule and the availability of the Marble Hill results prior to completion of NRC's review.
Consumers presented a technical overview of the annealing method.
They used Draft Regulatory Guide-1027, "Format and Content of Application for Approval
,/J for Thermal Annealing of Reactor Pressure Vessels," to present an outline of~
T
Contact:
Marsha Gamberoni, NRR
~~
415-3024 tOf.,.~~
9506280527 950618 11\\\\~"" 'f\\li. tf.\\\\ll6\\
':;A'\\\\
PDR ADOCK 05000255 1
UUil~
\\v~.
A PDR
~-*
\\~
~.
~
- ~
2 the Thermal-Annealing Operating Plan.
The outlirie is provided in.. Significant technical issues discussed during this portion of the meeting are presented below.
General Overview of Method/Expected Recovery The vessel will be annealed using an indirect gas heating system.
General sketches are provided in Attachment 3.
Ductwork and exhaust ventilation will be routed through the equipment and/or escape hatch.. Inside the reactor vessel, there will be five heating zones with two independent. burners per zone.
Palisades currently plans on a controlled thermal profile during heat-up with a 7-day soak at 850°F and a 25°F/hr cooldown. Temperature inside the rig at the source will be approximately 1400°F.
The ductwork route will be walked down during this outage which began on May 22, 1995.
Consumers predicts approximately an 80% or greater recovery from the annealing; however, it estimates only 40% recovery is required to reach its target of 2011, which includes recapturing the construction period.
Demonstration Project/Plant Comparison A demonstration project is scheduled for April 1996 at Marble Hill, a 4-loop Westinghouse plant. This demonstration project is being performed independent of the Palisades annealing program; however, it is expected to provide information useful to the Palisades project. Palisades is a Combustion Engineering plant with four inlet nozzles and two outlet nozzles. A sketch with dimensional comparisons of the Palisades and Marble Hill plants is provided in Attachment 3. Additional design comparisons are also provided in tables. The Palisades reactor vessel is supported on two inlet nozzles and one outlet nozzle.
The Marble Hill reactor vessel is supported on two inlet nozzles and two outlet nozzles.
A comparison of preliminary instrumentation locations between Palisades and Marble Hill is provided in Attachment 3.
Radiation Protection Shielding of primary sources will include the reactor vessel, the upper guide.
structure, and the core support barrel. The upper guide.structure will be air lifted with temporary shielding and will be placed in the core barrel. These components will be shielded by a wall with a top installed prior to draining.
Shielding will be placed around the reactor vessel and the heating system will be installed during reactor cavity draindown.
Dose rates are expected to be around 50 mrem/hr on the refueling deck (general area) and 500 mrem/hr in the cavity.
Total dose for the project is estimated at 215 person-rem. This is comparable to the annual dose for the plant. The most dose-intensive activity involves installation of instrumentation around the reactor. A summary of dose
~~~-est4mates/activity is provided in Attachment 3.
The estimates provided will be confirmed during this outage.
a"
_., i; J
~.'
~.:
3
. Structural *Issues
-*-The bioshield-temperature.will be monitored. during nor_!'lal operation_ following the installation of instrumentation this 6utage.
The temperatur~ limit
-at the bioshield is approximately*200°F..
The shield is cooled by embedded
~ooling coils. - OptiQnl for additional cooling during the annealing include
- augm~nted air c~olin~ of the area and chilled w~ter circul~ting through the embedd~d.cooling coil$.
Mechanical.Issues An init~al i~s~rvice inspect~on*of co~ponents will* be cond~cted as part of _the
.. e"fforts.
Thermal_ stress analysis will be performed using t~e ANSYS coinpµter.
. iode._ The analysis will i~cl~d~*the reactor vessel, _nozzles, Attache~ piping
, and.other discontinuities.
Surveillance Capsules..
\\
- Att'achments:. As* stated *c4>
cc w/at~: *see nex:t pa,ge -
DISTRIBUTION-:....
- See'attached li~t
- i DOCUMENT NAME-: - G.: \\WPDOCS\\PAL0606. SUM _
To receive a copy of thl* document, Indicate In the bOx: "C" ;= Copy* without attachmant/aricloaure "E" = Copy with 'attachment/enclosure "N" = No copy ' '
- SEE PREVIOUS CONCURRENCE OFFICE LA:PD31 c PM:PD31
£ BC:EMCB*
NAME DATE
~ I~ q~
06 16 95 OFFICIAL RECORD COPY
~. ~.
l,
, ~r e
Consumers Power Company cc:
Mr. Thomas J. Palmisano Plant General Manager Palisades Plant 27780 Blue Star Memorial Highway Covert, Michigan 49043 Mr. Robert A. Fenech Vice President, Nuclear Operations Palisades Plant 27780 Blue Star Memorial Highway Covert, Michigan 49043 M. I. *Miller, Esquire Sidley & Austin 54th Floor One First National Plaza Chicago, Illinois 60603 Mr. Thomas A. *Mc Ni sh, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Regional Administrator, Region III U.S. Nuclear Regulatory Commission
.001 Warrenville.Road
.Lisle, Illinois 60532-4351 Jerry Sarno Township Supervisor Covert Township 36197 M-140 Highway C6vert, ~ichigan 49043 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 U.S. Nuclear Regulatory Commission Resident Inspector's Office Palisades Plant 2778l Blue Star Memorial Highway
.Covert, Michigan 49043 Palisades Plant Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street P. 0. Box 30195 Lansing, Michigan 48909 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N. W.
Washington DC 20037 Michigan Department of Attorney General Special Litigation Division 630 Law Building P.O. Box 30212 Lansing, Michigan 48909 Mr. Dennis Harrison U.S. Department of En~rgy NE 451 Washington, DC 20585 Mr. Kurt M. Haas Plant Safety and Licensing Director Palisades Plant 27780 Blue Star Memorial Highway Covert, MI 49043 May 1995*
- ~.
w/att. I only EAdensam (E-mail)
CJamersrih OGC EJordan..
2.2003!).'
e summary dated: June 18, 1995
.,,,. r w
NAME Marsha Gamberoni Jack Strosnider Keith Wichman Robert Hermann Mike Parker Kamal Manely Cynthia Carpenter Ken Battige Chen Tan Robert Rothman David Shum MEETING ATTENDEES JUNE 6, 1995 Cayetano Santos, Jr.
Elinor Adensam Glenn Kelly Ed Hackett John Jacobsen Barry Elliot Glenn Dentel Carolyn Fairbanks John Tsao Andrea Wilford Lawrence Kokajko Gilbert Mill man Lambros Lois Iqbal Ahmed Alfred Taboada Micheal Vassilaros Charles Hinson Dick Smedley Jack Hanson Ken Powers John Kneeland George Goralski Wi 11 i am Becki us William Doolittle David Howell Rick Rishel Brad Maurer Glenn Campbell Wi 11 i am Server Jim Nakos John Warren Dennis Harrison Lynn Connor R. Borsum Bob Steele Nancy Chapman AFFILIATION NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC CPCo CPCo CPCo CPCo CPCo CPCo CPCo Westinghouse Westinghouse Westinghouse Cooperheat All Consulting DOE DOE DOE STS, Inc.
BWNT MPR Associates Bechtel ATTACHMENT I
- 1.
- 2.
- 3.
- 4.
CONSUMERS POWER/NRC VESSEL ANNEALING MEETING JUNE 6, 1995 Rockville, Maryland INTRODUCTION Purpose of Meeting Overall Schedule TECHNICAL OVERVIEW AGENDA Annealing Method Summary Recovery/Re-Embrittlement Summary OPEN DISCUSSION ON AFATA CONTENT Discuss Elements of the Attached AFATA Content Summary Which are of Particular Interest/Concern CLOSURE Identification of NRC AFATA Reviewers Timing of AFATA Submittal Action Items Future Meetings RESPONSIBLE Consumers Consumers NRC &
Consumers NRC &
Consumers DURATION 15 minutes
. 15 minutes 2 Hours 30 Minutes ATTACHMENT 2
i.*
. 't.
~
I
- 1.
- 2.
PALISADES PLANT REACTOR VESSEL ANNEAL THERMAL ANNEALING APPLICATION (AFATA) CONTENT THERMAL ANNEALING OPERATING PLAN I
COMMENTS Identification of general considerations No deviations from the
- a.
Identify reactor guidance of OG-1027 are
- b.
Provide reasons for annealing proposed.
- c.
Provide expected remaining operating life after annealing
- d.
Describe operating history of reactor (power-time-temperature history)
- e.
Specify reactor vessel beltline temperatures during reactor operation
- f.
Describe results of ongoing surveillance program (#
of specimens, initial values for RTnd* & USE, shifts of RT nd* and USE, also pre-anneal RTnd* and USE values Provide description of the reactor vessel No deviations from the
- a.
Detailed description of the reactor vessel guidance of OG-1027 are
- b.
Identify parts of vessel to be annealed proposed.
- c.
Include all vessel data used for determining the Thermal Annealing Operating Plan, the proposed
. inspections and tests, and the programs for recovery and re-embrittlement. For each heat of material in the reactor vessel beltline region include:
material compositions mechanical properties fabrication history and techniques NOE test results (in-shop) OSI)
Neutron fluence exposures if available, RT""'" (NB-2300), USE" (E185) material heats of base metal and weld metal to be used for measuring % recovery &
subsequent surveillance purposes to be identified
- d.
All vessel dimensions reported (diameter, wall thickness, cladding thickness, nozzle dimensions, flange dimensions, transition section dimensions, gaps between vessel & concrete structures, internal permanent structures & insulation)
- e.
Identify/describe attachments to reactor that could be affected by annealing operations, and expected effects, such as changes in properties of vessel insulation, effects of thermal growth of reactor vessel sliding support structures, and overheating of instrumentation and attachments
. 1 I
.L.
~. **'
I
- 3.
- 4.
PALISADES PLANT REACTOR VESSEL ANNEAL THERMAL ANNEALING APPLICATION (AFATA) CONTENT THERMAL ANNEALING OPERATING PLAN I
COMMENTS Equipment, components, and structures affected by thermal No deviations from the annealing guidance of DG-1027 are
- a.
Description of all equipment, structures, and proposed.
components that could be affected, either thermally or mechanically, by annealing operation and the expected effects (degradation of biological shield, effects of vessel growth, distortions on attached piping)
- b.
Identify significant thermal and mechanical loadings projected for each item and actions proposed to avoid damage from these loadings
- c.
Description of biological shield dimensions materials irradiation exposures unique features cooling provisions properties design temperature eliminations justification for exceeding design temperatures
- d.
Description of piping material types dimensions restraints design requirements (temperature, bending stress or strain limitations) identified NOE results (ISi)
- e.
Physical descriptions of other equipment or instrumentation that could be affected by the thermal annealing
- f.
Description of overall containment as it relates to core removal and storage as well as annealing Special requirements should be described in detail (storage of core internals)
Thermal annealing operating conditions No deviations from the
- a.
Description of proposed annealing parameters guidance of DG-1027 are (temperatures, times, HU and CD schedules) proposed.
- b.
Identify limitations and permitted variations in these conditions (axial, azimuthal, and through-wall gradients, permissible temperature profiles in the HU, CD, and steady state heating)
- c.
Describe test and analyses used to establish these annealing parameters 2
I
J..
~
I J
- 5.
- 6.
- 7.
PALISADES PLANT REACTOR VESSEL ANNEAL THERMAL ANNEALING APPLICATION (AFATA) CONTENT THERMAL ANNEALING OPERATING PLAN COMMENTS Description of annealing method, instrumentation, and No deviations from the procedures DG* 1027 guidelines are
- a.
Describe method of heating vessel in detail proposed.
- b.
Describe method of instrumentation in detail that permits on-line measurements of the temperatures at the locations needed to assess the entire temperature pr9file of the vessel, and adjacent structures and equipment; of the stress profiles including thermal gradients in the axial, azimuthal, and through thickness directions during all transient and steady*
state conditions of the annealing operation
- c.
Identify expected instrumentation accuracies, and reliability
- d.
Describe in detail the operational steps to be taken during the annealing operation including QA measures identify controls and how applied inst<!llation and removal of heat treatment equipment procedures to be used to control radioactive contamination drainage and drying of vessel prior to annealing precautions to preclude cooling water leakage into vessel during annealing Proposed annealing equipment No deviations from the
- a.
Description of equipment DG-1027 guidelines are heating apparatus proposed general* plant layout controls and instrumentation including redundancy controls equipment for measuring and recording the temperatures and temperature profiles support equipment ALARA provisions protection of instruments and equipment from temperature effects during annealing Thermal and stress analyses No deviations from the
- a.
Detailed thermal and structural analyses to establish DG-1027 guidelines are appropriate time and temperature profiles proposed
- b.
Specify the limiting parameters established by analyses, including the highest temperature, highest stress, and limiting HU and CD rates 3
l
'(
- I
- 8.
- 9.
- 10.
PALISADES PLANT REACTOR VESSEL ANNEAL THERMAL ANNEALING APPLICATION (AFATA) CONTENT THERMAL ANNEALING OPERATING PLAN I
COMMENTS Proposed annealing conditions; identify proposed annealing No deviations from the conditions (time, temperature, HU and CD rates, critical DG-1027 guidelines are stresses and strains) proposed.
ALARA Considerations No deviations from the
- a.
Description of steps to minimize occupational DG-1027 guidelines are exposure proposed.
- b.
Description of equipment and procedures for monitoring and control of airborne radioactive particles
- c.
Identification of precautions to avoid excessive exposure from radiation streaming when the reactor internals are being removed and stored, when the reactor coolant is removed from the reactor, and when the heating equipment is being moved into and out of the vessel
- d.
Description of steps to minimize exposure due to radioactive waste processing, radioactive materials decontamination, and radioactive waste shipment Summary of the Thermal Annealing Operating Plan No deviations from the DG-1027 guidelines are proposed.
4 I
1
- r:,
I PALISADES PLANT REACTOR VESSEL ANNEAL THERMAL ANNEALING APPLICATION (AFATA) CONTENT REOUALIFICATION INSPECTION AND TEST PROGRAM I COMMENTS
- 1.
Identification of the measurements and locations that will be Due to ALARA concerns and used to monitor the annealing process and. to verify that the physical access constraints, conditions of the Operating Plan are not exceeded; describe measurements will be measurement type, the number of measurements to be made optimized such that the for each component, measurement sensitivity, measurement proposed annealing frequency, and recording method conditions evaluated in the AFA TA are not exceeded and the annealing process can be adequately monitored. The intent of DG-1027 will be achieved.
- 2.
Description of the inspection program to affirm thc;it the No deviations from the annealing operation has not damaged the reactor vessel or DG-1027 quidelines are related equipment, components, or structures; describe the proposed.
type and number of examinations, the locations of the examinations, the acceptance criteria, qualification requirements, and reporting requirements
- 3.
Description of the test program to demonstrate the No deviations from the effectiveness of the annealing operation, and to assure that DG-1027 guidelines are the reactor vessel, attached piping and appurtenances, and proposed.
adjacent concrete have not been degraded; describe the type and number of tests, the locations/components of the tests, the purpose of the tests, the acceptance criteria, qualification requirements, and reporting requirements 5
I
. J '
l' PALISADES PLANT REACTOR VESSEL ANNEAL
-THERMAL ANNEALING APPLICATION (AFATA) CONTENT FRACTURE TOUGHNESS RECOVERY AND RE-COMMENTS EMBRITTLEMENT ASSURANCE PROGRAM
- 1.
Description of the methods to be used for quantifying the No deviations from the percent recovery of the RT nc1* and Charpy USE values guidance of DG-1027 are proposed.
- 2.
Description of the methods to be used for estimating the re-No deviations from the embrittlement rate of the RT nc1i and Charpy USE guidance of DG-1027 are proposed.
- 3.
Oescription of the methods to be used for monitoring the re-No deviations from the embrittlement rate of the RT nd* and Charpy USE during guidance of DG-1027 are subsequent plant operation proposed.
6
- 1.
2.-
- 3.
- 4.
- 5.
- 6.
PALISADES PLANT REACTOR VESSEL ANNEAL THERMAL ANNEALING APPLICATION (AFATA) CONTENT CERTIFICATION OF ANNEALING PROCESS AND COMMENTS RECOVERY ESTIMATE Description of Overall Process AFA TA will describe methodology that will be used for certification Evaluation of Inspection and Tests AFATA will describe methodology that will be used for certification Determination of Percent Recovery AFATA will describe methodology that will be used for certification Determination of Re-embrittlement Rate AFATA will describe methodology that will be used for certification Description of Modified Surveillance Plan AFATA will describe methodology that will be used for certification Allowable Operating Period AFATA will describe methodology that will be used for certification 7
j f
I CONSUMERS POWER/NRC VESSEL ANNEALING MEETING
_ JUNE 6, 1995 Rockville, Maryland PURPOSE To obtain a common understanding of the Palisades vessel annealing project's status by Consumers Power providing an:
Overview of the Annealing Process Overview of the Annealing Project's Schedule.
To begin Application for Approval for Thermal Annealing (AFATA) open communications between Consumers Power and the NRC.
To provide an opportunity for discussion to obtain an understanding of any issues which the NRC believes are critical to the overall approval of the AFATA.
ATTACHMENT 3
a *
. I,,
- 1.
- 2.
- 3.
- 4.
CONSUMERS POWER/NRC VESSEL ANNEALING MEETING JUNE 6, 1995 Rockville, Maryland INTRODUCTION Purpose of Meeting Overall Schedule TECHNICAL OVERVIEW AGENDA Annealing Method Summary Recovery/Re-Embrittlement Summary OPEN DISCUSSION ON AFATA CONTENT Discuss Elements of the Attached AFATA Content Summary Which are of Particular Interest/Concern CLOSURE Identification of NRC AFATA Reviewers Timing of AFATA Submittal Action Items Future Meetings RESPONSIBLE Consumers Consumers NRC &
Consumers NRC &
Consumers DURATION 15 minutes 15 minutes 2 Hours 30 Minutes
Proposed Palisades 1998 Annealing Schedule 1995 Outage Work Conceptual Design Phase (I)
NRC Approval of 10CFR50.66 & RG-1027 6/4/1995:
1995 1996 1997 1998 MJJASONDJFMAMJJASONDJFMAMJJASONDJFMAMJJASON Jz; IL!
616*
- _9**'-~--'-*--*'--*'----'--~---~*' :.~:_,_.....,_,,__,.. _____,__...,....--..--....---.---.,......,_..---,___,_-; : : ' '
~~
~~
t--+-L~---i... -i -
' Submittal of AFATA i
j
&1si 1w1 ___ ~--~-~--~~-~~~--~~-U~-----
9/1
- f-------------~--"---',__.____._ _ _..___>--+----+--+--'~---+--..._.__,_--;._~___..._....__~_...___.__-+--+--+---+--__,--+-*---+---l--i---+-
'---i----'*******'-**
Detailed Design Phase (II)
- a
'10/3!
+____..,__.__ ___
~*
IL i 9/28:
--~
~~---'.
DOE Annealing Demo at
- Preparation * *
- Anneal :
- Final Report Marble Hill NRC Approval of AFATA a*;~*llllil......
llilli..
'**~,~*------~IL~i 6/1 '
- 4/1 : 6/1
- i11/1:
- i
- 6/1.
+-,...._.,...--+-_,_: -'-: -i Public Workshops
- .t.
IL:
- ! ' ' : j
- 6/1 :
- 1211
.. ----------*--------+--*--;--.. :._._; __.c.._+... -'
-~--' --c--.;--;---;--.,..._ ' --'---'-*
Construction Phase (111)
Implementation Phase (IV)
Certification of Annealing Process Submittal f\\JRC Restart "Approval"
- a'
- 1013
.-_i-~--~--'--e.
]
f
-;--.,..~-+--;---;--;--~--~~-~--*;........ _:_._+------...:.. *-. -- --~ *-
~
, IL,
2125
--;----'---;--;---~--;-
~
- ---~-**-- ~
-~*-'- -.....
2125 IL 8/2 8/10 A
A I
'II I
TECHNICAL OVERVIEW ANNEALING METHOD
SUMMARY
HEATING METHODS AND CONTROLS INSTRUMENTATION SHIELDING
N127.02 In Containment G095JUN01 Shielding/ I
~- Structural Support
- =-- Insulation I
+---Reactor Vessel I
I I
I I
COOPERHEAT
- 6-595
-- Exhaust 111!11[11!
Outside Containment
N127.03 G095JUN01 COOPERHEAT Heating Chamber Q)
Q) c c
0 Q) 0 N
c N
Ol :J Ol c -
c
+::
Q)
(1i cu Cil Q)
Q)
I I
Control Chambers
- 6-595 e
.'llmlllU.........
~*10C8 I.
I.
I
- I.
- I.
I.
I I
- I
'I
- A TT ACHMEN 1 M - 5 SCCTION A-A
er ATTACHMENT M-8 A.
EQUATION TECHNICAL OVERVIEW RECOVERY/RE-EMBRITTLEMENT
SUMMARY
EXISTING SURVEILLANCE MATERIAL SUPPLEMENTAL SURVEILLANCE PROGRAM
'i
'I,....
- l.
.e THERMAL ANNEALING APPLICATION CONTENT THERMAL ANNEALING OPERATING PLAN REQUALIFICATION INSPECTION AND TEST PROGRAM FRACTURE TOUGHNESS RECOVERY AND RE-EMBRITTLEMENT ASSURANCE PROGRAM CERTIFICATION OF ANNEALING PROCESS AND RECOVERY ESTIMATE
THERMAL ANNEALING APPLICATION CONTENT THERMAL ANNEALING OPERATING PLAN 1.
Identification of general considerations
- 2.
Provide description of the reactor vessel
- 3.
Equipment, components, and structures affected by thermal annealing
- 4.
ThermaJ annealing operating conditi9ns
- 5.
Description of annealing method, instrumentation, and procedures
- 6.
Proposed annealing equipment
- 7.
Thermal and stress analyses
- 8.
Proposed annealing conditions
- 9.
A LARA Considerations
- 10. Summary of the Thermal Annealing Operating Plan
.I.** I THERMAL ANNEALING APPLICATION CONTENT REQUALIFICATION INSPECTION AND TEST PROGRAM 1.
Identification of the measurements and locations
- 2.
Description of the inspection program
- 3.
Description of the test program
THERMAL ANNEALING APPLICATION CONTENT FRACTURE TOUGHNESS RECOVERY AND RE-EMBRITTLEMENT ASSURANCE PROGRAM 1.
Description of the methods for quantifying the percent recovery
- 2.
Description of the methods for estimating the re-embrittlement rate
- 3.
Description of the methods for monitoring the re-embrittlement rate
- I 9
THERMAL ANNEALING APPLICATION CONTENT CERTIFICATION OF ANNEALING PROCESS AND RECOVERY ESTIMATE 1.
Description of Overall Process
- 2.
Evaluation of Inspection and Tests
- 3.
Determination of Percent Recovery
- 4.
Determination of Re-embrittlement Rate
- 5.
Description of Modified Surveillance Plan
- 6.
Allowable Operating Period
I.. *~ I Di mens i ona l Campa ri son of Pals i a des and Marble Hi 11 Reactor Vessel Marble Hill Palisades I
165.5" 166" Minimum I.D.
I I
Bottom of Nozzle Weld to Top of Active Fuel
~
1 34" t
36" 144" lllf-J 173" Active Fuel Height Reactor Vessel I.D.
132" I i;-
8.63" Minimum RV Base Metal Thickness 8.50" jp?i2222222f'i'?t1
e PALISADES AND MARBLE HILL VESSEL DESIGN COMPARISONS I
Vessel Dimensions Comearisons I
Dimension (inches)
Marble Palisades Hill Vessel Clad 1.0. at Beltline 173 172 Minimum Vessel Base Metal 8.63 8.50 Beltline Thickness Nominal Claddinq Thickness 0.16 0.25 Active Fuel Height 144 132 Bottom of Nozzle Weld to Top
=34 0
=36 of Active Fuel Minimum Vessel 1.0.
166
. =165 I
Other Design Comearisoris I
I I
I I
Design Feature Marble Palisades Hill Number of Hot and Cold Leg 8
6 Nozzles Thermal Expansion Yes Yes Accommodated by Movement of PCS Equipment Type of Vessel Support Nozzle Nozzle Supported Supported 2 Inlets 2 Inlets 2 Outlets 1 Outlet Cladding Material, Weld 308/309 304 S.S.
Deposited S.S.
Original Vessel Heat 1100 -
1100 -
Treatment l lSO°F 1175°F Exterior Vessel Beltline Metal Metal Insulation Reflective Reflective Palisades/MarbleHillDesignComparisons6*2*95
f AL 15/lPE..S VE.5.SEL 1eo 0
&.fer""<e. CE P""J 11/BA SJ.. 1Z.
.'\\
I Ske.1-c~ 6*J*15 <fl/G-
4 I
I.* '\\*;""
I
~:
PALJ5AP£S
/?EAcTOK VE.S.SEL
' ~
- ~
~
0
~
l"\\ ~
ll r, so " PIA s,.,,,r /foul£ VESJ£' SIA°'
l"I II 110111.c wn.p
~
~
~
~
F~
~
0
~
~
~
. 14.
~
17z" 91A -!..:Z.NN£-'t C~A~
ct)
~
l 0--
N
~
- 8. S'l1 **,.,,,,
!'UIS o.z.s* Ko~ C"1'.P
dtn;; ""'9'/,, 'ro SW1d' l'llt,,/,,.,
- JJ>tS UJ'Ult Uty.l.JJ1-'"0 00'£LI
~j
..., ~
771/(
~
~
~
~
(\\
~
I'
~
~
l..J N
~
~
N 0
lo\\
t
'1 I.._ I t.,.~
- I COMPARISON OF INSTRUMENTATION LOCATIONS* PALISADES AND MARBLE lilLL (PRELIMINARY)
Zone Description I Surface I Instrument I
Palisades I Marble Hill Bottom of Reactor Vessel OD of RV Thermocouple I
I Displacement I
I Srrain Gauge 0
I.
Coincident with Core Suppo11 OD of RV Thennocouple 3
7 Lugs Vessel Beltline. Mid-Region OD of RV Thennocouple 3
7 Displacement 3
4 Vessel Top of Beltline into OD of RV Thennocouple 3
7 Transition RV Nozzle. Bottom Side OD of RV Thermocouple 0
8 Strain Gauge 0
8 RV Nozzle. Upper Side OD of RV Thermocouple 0
7 RV Becween ~ozzle and Flange OD of RV Thermocouple 0
7 RV Flange OD of RV Thermocouple 0
7 Nozzle to Pipe Weld. Lower OD of RV Thermocouple 0
8 Side Strain Gauge 0
8 Nozzle to Pipe Weld. Upper OD of RV Thermocouple 0
8*
Side Strain Gauge 0
8 Nozzle Suppor1 On suppor1 Thermocouple 2
4 Reactor Cavity Liner, Beltline
- On liner Thermocouple 2
4 Region Each Loop Located Midway On piping Displacement 6'
8 Between SIG or Pump & Vessel Outside of Bioshield Wall Nozzle to Pipe Weld. Bottom ID of RV Thermocouple 6
8 Side Nozzle to Pipe Weld. Upper ID of RV Thermocouple 6
8 Side Vessel Beltline, Heating Zone ID of RV Thermocouple 42 42 RV Shell Above RV Nozzles ID of RV Thermocouple 12 12 TOT AL LOCATIONS OD or RV Thermocouple 14 75 Displacement 10 13 Strain Gauge 0
25 TOTAL LOCATIONS ID or RV Thermocouple 66 70 I
e e
AFATA THERMAL AND STRESS EVALUATIONS AFATA will include a complete evaluation for the following components-based on.
the conceptual design of the annealing equipment which will be defined in the AF AT A.
Reactor Vessel Nozzles PCS Piping, Restraints, and Supports Biological Shielding Reactor Vessel Insulation Flow Skirt Cladding Capsule Holders Reactor Vessel Flange Instrumentation Other Components as Determined during the Conceptual Review Effort Thermal& StressEvaluationsFor AFAT A6-1-9 5
PALISADES THERMAL ANNEALING PROGRAM PLAN TO ACHIEVE ALARA GOALS
- 1.
Thermal Annealing to be performed utilizing indirect gas heating system, can be installed during Reactor Cavity draindown.
- 2.
Upper guide structure would be stored dry inside the core support barrel behind temporary shielding during the thermal anneal.
- 3.
As many activities as practical are performed with the reactor cavity flooded utilizing long handle tools.
- 4.
Appropriate instrumentation will be installed on the Palisades Reactor Vessel taking advantage of the experience at Marble Hill, to minimize dose for installation at Palisades.
.~.:..,_ ~'...
e e
-c:*
ATTACHMENT H-2 PALISADES THERMAL ANNEAL PROGRAM
- DOSE ASSESSMENTS ALTERNATIVE CASE 1995 PROGRAM AVERAGE DOSE TOTAL DURATION RATE CREW DOSE
!.Q LOCATION lhtl
!mr/hr)
SIZE
[Man-Rem!
Complete Containment Walkdown DECK 100 5
4 2.0 2
Install Instrumentation Around Vessel SUMP 2.5 4000 10.0 TOTAL DOSE ASSESSMENT
- 1995 PROGRAM 12.0 199711998 PROGRAM.
3 Install temperature resistant RV stud hole plugs if required DECK 12 5
4 0.2 4
Move equioment into containment DECK 60 5
4 1.2 5
EQUIPMENT SETUP 6
Assemble furnace in preparation for test DECK 144 5
4 2.9 7
Install/setup support equioment DECK 276 5
4 5.5 8
Complete furnace ducting DECK 24 2
4 0.2 9
Install instrumentation around RX SUMP 40
- OOO 1
t60.0 10 Place UGS into temporary storage stand DECK 6
10 4
0.2 11 Remove CSB and place into temporary stcrage stand DECK 8
30 4
1.0 12 Place temporary shield at EL 649 around cavity/move UGS to CSB.
DECK 8
60 4
1.9 DECK 3
20 4
0.2 13 Install temporary shielding around internals and top cap DECK 12 60 4
2.9 DECK 8
30 4
1.0.
14 Perform reactor vesselAntemals pre anneal measurements DECK 24 30 4
2.9 15 PERFORM PRE ANNEAL ISi
- BY OTHERS 16 Perform furnace containment test DECK 48 10 4
1.9 17 Remove annealing capsules from the RV DECK 12 3o 4
1.4.
18.
Drain reactor cavity to vessel flange DECK 18 60 4
4.3 19 Install nozzle plugs if required DECK 12 60 4
2.9 20 Cavity decorvVentilation hookup/RV purge/Cavity seal ring removed CAVrTY 9
500 2
9.0 21 Lower furnace into RX/drain RV/system walkdown CAVrTY 0.5 500 1
0.3 DECK 4
60 3
0.7 22 System heatup to temperature DECK 45 15 1
0.7 23 Anneal reactor vessel DECK 168 15 1
2.5.*
24 Cooldown to ambient USING FORCED AIR DECK 144 15 1
2.2 25 Pull fumacalfill reactor vessel and cavity CAVrTY 4
500 2
4.0 DECK 24 15 1
0.4~
26 Remove internals shielding/move UGS to temp. stand DECK 12 30 4
1.4 27 Make confirmation measurements DECK 24 30 4
2.9 28 PERFORM POST ANNEAL ISi
- BY OTHERS 29 Complete moveout of containment DECK 24 5
4 0.5 30 INST ALL CSB
- BY OTHERS 31 FUEL. INSTALL UGS, INSTALL HEAD. REASSEMBLY. STARTUP TOTAL DOSE ASSESSMENT
- 199711998 PROGRAM 2 JS
I
(]
J I
PLANNED PALISADES REACTOR VESSEL SURVEILLANCE PROGRAM' Page 1 of 1 6/4/1995 199s I 1996 I 1991 I 199s 11999 I 2000 I 2001 I 2002 I 2003 I 2004 I 2oos I 2006 2007 EOC11 EOC12 EOC13 EOC14 EOC15 EOC16 EOC17 EOC18 EOC19 Cycle#
~
~,
SA-60-1 SA-60-2 A-60 lX
,, 'I
!XI
.a.
' I
- ! SA-240-1 A-240 IX I., 'I W-100 I., 'I i ' ' i T-150 i
.0.
i W-280 i
~..
W-260
.4..
W-80 l ~
i i
EOC Date
,~
5/95 12/96 5/98 11/99 4/01 9102 3/04 8/05 1107 cg] Install Capsule
.6. Remove/Analyze Capsule
~ Remove Capsule Remove/Anneal/Install Capsule
!YI Remove/Analyze/Reconstitute/Anneal/Analyze
. I
PALISADES REACTOR VESSEL ANNEAL AND REEMBRITTLEMENT RATE ASSURANCE PROGRAM SUPPLEMENTAL CAPSULES SA-60-1 AND SA-240-1 I
MATERIAL I
18 MM CHARPY I
L-T CHARPY I
W5214
- 36 34B009
- 36 27204 +
36 HSST02 12 STEAM GENERATOR WELDS HEAT TREATED
@1160° F FOR 2
HOURS.
COOLED @ 100°F
+
LINDE 1092 VS 124 LEAD FACTOR > 10 RECONSTITUTE AND TEST 1h OF *IRRADIATED SPECIMENS ANNEAL, RECONSTITUTE AND TEST 1h OF IRRADIATED SPECIMENS ANNEAL AND INSTALL 1h OF IRRADIATED SPECIMENS IN SA-60-2 I
CAPSULE W-100 MATERIAL I
CHARPY I
BASE METAL (L-T) 12 BASE METAL <T-U 12 3277 12 TEST IRRADIATED SPECIMENS ANNEAL, RECONSTITUTE AND TEST % OF IRRADIATED SPECIMENS ANNEAL AND INSTALL % OF IRRADIATED SPECIMENS IN SA-60-2
PALISADES REACTOR VESSEL ANNEALING RECOVERY PROGRAM AVAILABLE IRRADIATED TESTED CHARPY SPECIMENS I
MATERIAL I W-290 I W-110 I A-240 I BASE METAL (L-T) 12 12 12 BASE METAL (T-L) 12 12 HSSTOl 12 3277 12 12 12 SURVEILLANCE CAPSULE REMOVAL CAPSULE END OF CYCLE FLUENCE <1019 N/ CM2 )
A-240 2 <1978) 4.60 W-290 5 <1983) 1.09 W-110 10 <1993) 1.78
. VESSEL FLUENCE <1019 N/CM2 )
END OF CYCLE
@Oo
@16°
@30° 13 <1998)
- 1. 37
- 1. 92 1.43
DATE*
June 28-30, 1995 Mid-July 1995 August 24 & 25, 1995 FUTURE MEETINGS LOCATION NRC staff tour of Palisades Proof of principal test of heater (Piscataway, New Jersey)
Marble Hill plant tour ATTACHMENT 4