ML051370110
| ML051370110 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/12/2005 |
| From: | Vanderheyden G Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EA-03-009, TAC MC5705 | |
| Download: ML051370110 (8) | |
Text
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George Vanderheyden Vice President Calvert Cliffs Nuclear Power Plant Constellation Generation Group, LLC 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410.495.4455 410.495.3500 Fax I
Constellation Energy May 12,2005 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
SUBJECT:
Document Control Desk Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 60 Days After Plant Restart Report - First Revised NRC Order EA-03-009, Interim Inspection Requirement for Reactor Pressure Vessel Heads at Pressurized Water Reactors
REFERENCES:
(a)
Letter from Mr. R. W. Borchardt (NRC) to Holders of Licenses for Operating Pressurized Water Reactors, dated February 20, 2004, Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors (b)
Letter from Mr. C. F. Holden, Jr. (NRC) to Mr. G. Vanderheyden (CCNPP), dated March 11, 2005, Calvert Cliffs Nuclear Power Plant, Unit No. 2 - Relaxation of the Requirements of First Revised Order Modifying License (EA-03-009),
Regarding Reactor Pressure Vessel Head Inspections (TAC No. MC5705)
The purpose of this letter is to forward Calvert Cliffs Nuclear Power Plant, Inc.'s "60 Days After Plant Restart" report requested in Section IV(E) of First Revised Nuclear Regulatory Commission Order EA-03-009 (Reference a). Calvert Cliffs Nuclear Power Plant completed the inspection of Unit 2 reactor vessel head penetrations required by Reference (a), as modified by Reference (b), and returned the plant to operation on March 16, 2005.
Document Control Desk May 12, 2005 Page 2 Attachment (1) to this letter provides the requested report. Should you have questions regarding this matter, please contact Mr. L. S. Larragoite at (410) 495-4922.
Ve I you s, GV/MJY/bjd
Attachment:
(1) 60 Days After Plant Restart Report - First Revised NRC Order EA-03-009, Interim Inspection Requirement for Reactor Pressure Vessel Heads at Pressurized Water Reactors cc:
R. V. Guzman, NRC S. J. Collins, NRC Resident Inspector, NRC R. 1. McLean, DNR
ATTACHMENT (1) 60 DAYS AFTER PLANT RESTART REPORT FIRST REVISED NRC ORDER EA-03-009, INTERIM INSPECTION REQUIREMENT FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS Calvert Cliffs Nuclear Power Plant, Inc.
May 12, 2005
ATTACHMENT (1) 60 DAYS AFTER PLANT RESTART REPORT -
FIRST REVISED NRC ORDER EA-03-009, INTERIM INSPECTION REQUIREMENT FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS Calvert Cliffs Nuclear Power Plant completed the inspection of Unit 2 reactor vessel head penetrations required by Nuclear Regulatory Commission (NRC) Order EA-03-009 (Reference 1), as modified by Reference (2), and returned the plant to operation on March 16, 2005.
Calvert Cliffs Unit 2 is in the highest susceptibility category as a result of having accumulated greater than 12 Effective Degradation Years, which was calculated in accordance with the methodology provided in the Order. For those plants in the High category, reactor pressure vessel (RPV) head and head penetration nozzle inspections must be performed using the following techniques every refueling outage; (a)
Bare metal visual examination of 100% of the RPV head surface (including 3600 around each RPV head penetration nozzle).
For RPV heads with the surface obscured by support structure interferences which are located at RPV head elevations downslope from the outermost RPV head penetration, a bare metal visual inspection of no less than 95% of the RPV head surface may be performed provided that the examination shall include those areas of the RPV head upslope and downslope from the support structure interference to identify any evidence of boron or corrosive product. Should any evidence of boron or corrosive product be identified, the licensee shall examine the RPV head surface under the support structure to ensure that the RPV head is not degraded.
(b)
For each penetration, perform a nonvisual NDE [nondestructive examination] in accordance with either (i), (ii), or (iii):
(i)
Ultrasonic testing of the RPV head penetration nozzle volume (i.e., nozzle base material) from 2 inches above the highest point of the root of the J-groove weld (on a horizontal plane perpendicular to the nozzle axis) to 2 inches below the lowest point at the toe of the J-groove weld on a horizontal plane perpendicular to the nozzle axis (or bottom of the nozzle if less than 2 inches); OR from 2 inches above the highest point of the root of the J-groove weld (on a horizontal plane perpendicular to the nozzle axis) to 1.0-inch below the lowest point at the toe of the J-groove weld (on a horizontal plane perpendicular to the nozzle axis) and including all RPV head penetration nozzle surfaces below the J-groove weld that have an operating stress level (including all residual and normal operation stresses) of 20 ksi tension and greater. In addition, an assessment shall be made to determine if leakage has occurred into the annulus between the RPV head penetration nozzle and the RPV head low-alloy steel.
(ii)
Eddy current testing or dye penetrant testing of the entire wetted surface of the J-groove weld and the wetted surface of the RPV head penetration nozzle base material from at least 2 inches above the highest point of the root of the J-groove weld (on a horizontal plane perpendicular to the nozzle axis) to 2 inches below the lowest point at the toe of the J-groove weld on a horizontal plane perpendicular to the nozzle axis (or the bottom of the nozzle if less than 2 inches); OR from 2 inches above the highest point of the root of the J-groove weld (on a horizontal plane perpendicular to the nozzle axis) to 1.0-inch below the lowest point at the toe of the J-groove weld (on a horizontal plane perpendicular to the nozzle axis) and including all RPV head penetration nozzle surfaces below the J-groove weld that have an operating stress level (including all residual and normal operation stresses) of 20 ksi tension and greater.
I
ATTACHMENT (1) 60 DAYS AFTER PLANT RESTART REPORT -
FIRST REVISED NRC ORDER EA-03-009, INTERIM INSPECTION REQUIREMENT FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS (iii)
A combination of (i) and (ii) to cover equivalent volumes, surfaces, and leak paths of the RPV head penetration nozzle base material and J-groove weld as described in (i) and (ii).
Substitution of a portion of a volumetric exam on a nozzle with a surface examination may be performed with the following requirements:
- 1. On nozzle material below the J-groove weld, both the outside diameter and inside diameter surfaces of the nozzle must be examined.
- 2.
On nozzle material above the J-groove weld, surface examination of the inside diameter surface of the nozzle is permitted provided a surface examination of the J-groove weld is also performed.
CCNPP Inspection Results The bare metal visual examination was accomplished with no indications of leakage. Every penetration was examined 3600 around. The head was clean, with no evidence of degradation of any kind.
The vent line and in-core instrument (ICI) penetrations were examined using a rotating ultrasonic testing (UT) probe. These examinations included all of the nozzle material from the bottom of the nozzle to greater than 2 inches above the J-groove weld. There were no indications of cracking or degradation.
For the ICI penetrations, an assessment to determine if leakage has occurred into the interference fit zone w'as performed using an ultrasonic technique. No evidence of leakage was found.
For the vent line, a UT leakage path assessment could not be performed because the vent line was installed with a clearance fit. For the vent line the assessment to determine whether leakage has occurred into the interference fit zone was accomplished by performing an eddy current examination (ET) of the J-groove weld surface. No evidence of leakage was found.
All of the control element drive mechanism (CEDM) penetrations were inspected using UT techniques.
The assessment to determine if leakage has occurred into the interference fit zone was performed using an ultrasonic technique. No evidence of leakage was found.
Above the weld, all nozzles were examined to a minimum of 1.2 inches above the highest point of the root of the J-groove weld (on a horizontal plane perpendicular to the nozzle axis). Fifteen of the CEDM nozzles were UT inspected at least 2 inches above the highest point of the root of the J-groove weld in accordance with the requirements of the First Revised NRC Order (Reference 1).
Fifty CEDM penetration nozzles did not meet this requirement.
Relaxation was requested and granted for these nozzles.
Below the weld, six CEDM nozzles (3, 14, 18, 26, 38, and 46) were successfully scanned for the full length below the toe of the weld. The remaining 59 CEDM nozzles where examined to a minimum of 0.35 inches below the toe of the weld. Relaxation was requested and granted for these nozzles.
Results of the RPV head penetration examinations are provided in Table 1.
2
ATTACHMENT (1) 60 DAYS AFTER PLANT RESTART REPORT -
FIRST REVISED NRC ORDER EA-03-009, INTERIM INSPECTION REQUIREMENT FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS
REFERENCES:
(1) Letter from Mr. R. W. Borchardt (NRC) to Holders of Licenses for Operating Pressurized Water Reactors, dated February 20, 2004, Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors (2) Letter from Mr. C. F. Holden, Jr. (NRC) to Mr. G. Vanderheyden (CCNPP), dated March 11, 2005, Calvert Cliffs Nuclear Power Plant, Unit No. 2 - Relaxation of the Requirements of First Revised Order Modifying License (EA-03-009), Regarding Reactor Pressure Vessel Head Inspections (TAC No. MC5705) 3
ATTACHMENT (1) 60 DAYS AFTER PLANT RESTART REPORT -
FIRST REVISED NRC ORDER EA-03-009, INTERIM INSPECTION REQUIREMENT FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS Table I Calvert Cliffs Unit 2 (Spring 2005)
Extent of UT Coverage in RPV Head Nozzle Material Coverage Coverage BelovWeld Circumferential Scan Type (Blade Leak Path Nozzle Above Toe on the Coverage Probe / Rotating)
Examined to Assessment Pen Angle Weld Root Downhill Side Achieved Axial Blade: A End of Possible?
on Uphill (in)
(Degrees)
Circ Blade: C Nozzle (Yes / No)
(in)
(Note 1)
CEDM 1 0.0 1.70*
1.00*
360 C
No Yes CEDM 2 11.1
>2 0.51*
360 C
No Yes CEDM 3 11.1 1.91*
N/A 360 A/C Yes Yes CEDM 4 11.1 1.50*
0.65*
360 C
No Yes CEDM 5 11.1
>2 0.85*
360 C
No Yes CEDM 6 12.0
>2 0.70*
360 C
No Yes CEDM 7 12.0 1.71*
0.75*
360 C
No Yes CEDM 8 12.0 1.20*
0.85*
360 C
No Yes CEDM 9 12.0
>2 0.80*
360 C
No Yes CEDM 10 22.6 1.92*
0.45*
360 C
No Yes CEDM 11 22.6 1.90*
0.60*
360 C
No Yes CEDM 12 22.6
>2 0.40*
360 C
No Yes CEDM 13 22.6
>2 0.80*
360 C
No Yes CEDM 14 24.1
>2 NIA 360 A
Yes Yes CEDM 15 24.1 1.90*
0.50*
360 C
No Yes CEDM 16 24.1
>2 0.40*
360 C
No Yes CEDM 17 24.1
>2 0.45*
360 C
No Yes CEDM i8 25.5 1.61*
N/A 360 A
Yes Yes CEDM 19 25.5 1.50*
0.70*
360 C
No Yes CEDM 20 25.5 1.61*
0.50*
360 C
No Yes CEDM 21 25.5 1.80*
0.60*
360 C
No Yes CEDM 22 25.5 1.55*
0.40*
360 C
No Yes CEDM 23 25.5 1.61*
0.40*
360 C
No Yes CEDM 24 25.5
>2 0.40*
360 C
No Yes CEDM 25 25.5
>2 0.74*
360 C
No Yes CEDM 26 29.3 1.81*
N/A 360 A
Yes Yes CEDM 27 29.3 1.75*
0.60*
360 C
No Yes CEDM 28 29.3
>2 0.40*
360 C
No Yes CEDM 29 29.3 1.80*
0.75*
360 C
No Yes CEDM 30 29.3
>2 0.45*
360 C
No Yes CEDM 31 29.3
>2 0.35*
360 C
No Yes CEDM 32 29.3 1.84*
0.50*
360 C
No Yes CEDM 33 29.3
>2 0.75*
360 C
No Yes CEDM 34 34.9 1.66*
0.80*
360 C
No Yes CEDM 35 34.9 1.48*
0.40*
360 C
No Yes CEDM 36 34.9 1.61*
0.85*
360 A/C No Yes CEDM 37 34.9 1.79*
0.85*
360 C
No Yes CEDM 38 38.5 1.63*
N/A 360 A
Yes Yes CEDM 39 38.5 1.30*
0.45*
360 C
No Yes CEDM 40 38.5 1.30*
0.40*
360 C
No Yes 4
ATTACHMENT (1) 60 DAYS AFTER PLANT RESTART REPORT -
FIRST REVISED NRC ORDER EA-03-009, INTERIM INSPECTION REQUIREMENT FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS Table 1 Calvert Cliffs Unit 2 (Spring 2005)
Extent of UT Coverage in RPV Head Nozzle Material Coverage Coverage Below Weld Circumferential Scan Type (Blade E
Leak Path Nozzle Above Toe on the Coverage Probe / Rotating)
Examined to Assessment Pen Angle on Uill Downhill Side Achieved Axial Blade: A Nozzle Possible?
(in)
Upil (in)
(Degrees)
Circ Blade: C Noze(Yes
/No)
___(in)
(N ote_1)_
CEDM41 38.5 1.55*
0.50*
360 C
No Yes CEDM 42 38.5 1.75*
0.45*
360 C
No Yes CEDM43 38.5 1.77*
0.70*
360 C
No Yes CEDM44 38.5 1.27*
0.65*
360 C
No Yes CEDM 45 38.5 1.40*
0.80*
360 C
No Yes CEDM 46 41.8 1.56*
N/A 360 A
Yes Yes CEDM47 41.8 1.21*
0.40*
360 C
No Yes CEDM48 41.8 1.50*
0.45*
360 C
No Yes CEDM49 41.8 1.44*
0.64*
360 No Yes CEDM50 41.8 1.58*
0.60*
360 C
No Yes CEDM51 41.8 1.30*
0.51*
360 C
No Yes CEDM 52 41.8 1.60*
0.63*
360 C
No Yes CEDM 53 41.8 1.47*
0.60*
360 C
No Yes CEDM54 42.5 1.60*
0.55*
360 C
No Yes CEDM 55 42.5 1.67*
0.45*
360 A/C No Yes CEDM56 42.5 1.75*
0.90*
360 C
No Yes CEDM 57 42.5 1.60*
0.40*
360 C
No Yes CEDM58 42.5 1.55*
0.55*
360 C
No Yes CEDM59 42.5 1.47*
0.65*
360 C
No Yes CEDM 60 42.5 1.25*
1.51*
360 A
No Yes CEDM 61 42.5 1.60*
0.50*
360 C
No Yes CEDM 62 42.5 1.66*
0.50*
360 C
No Yes CEDM 63 42.5 1.36*
0.50*
360 C
No Yes CEDM64 42.5 1.35*
0.50*
360 C
No Yes CEDM 65 42.5 1.37*
0.50*
360 C
No Yes ICI 66 54.8
>2 N/A 360 Rotating Yes Yes ICI 67 54.8
>2 N/A 360 Rotating Yes Yes ICI 68 54.8
>2 NIA 360 Rotating Yes Yes ICI 69 54.8
>2 N/A 360 Rotating Yes Yes ICI 70 54.8
>2 N/A 360 Rotating Yes Yes ICI 71 54.8
>2 N/A 360 Rotating Yes Yes ICI 72 54.8
>2 N/A 360 Rotating Yes Yes ICI 73 54.8
>2 N/A 360 Rotating Yes Yes Vent-Line 0-11
>2 N/A 360 Rotating/ECT Yes N/A**
Note 1: N/A indicates coverage to the end of the nozzle Relaxation from the Order requirement was granted.
Leak path assessment performed by ET of weld.
5