ML031600461
| ML031600461 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/03/2003 |
| From: | Katz P Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EA-03-009, TAC MB7752, TAC MB7753 | |
| Download: ML031600461 (7) | |
Text
Peter E. Katz 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 Constellation I
Energy Group June 3, 2003 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 - NRC Order EA-03-009, Interim Inspection Requirement for Reactor Pressure Vessel Heads at Pressurized Water Reactors (TAC No. MB7753)
REFERENCES:
(a)
Letter from Mr. S. J. Collins (NRC) to Holders of Licenses for Operating Pressurized Water Reactors, dated February 11, 2003, Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors (EA-03-009)
(b)
Letter from Mr. S. A. Richards (NRC) to Mr. P. E. Katz (CCNPP), dated April 18, 2003, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 -
Relaxation of the Requirements of Order (EA-03-009), Regarding Reactor Pressure Vessel Head Inspections (TAC Nos. MB7752 and MB7753)
The purpose of this letter is to forvard Calvert Cliffs Nuclear Power Plant, Inc's "60 Days After Plant Restart" report requested in Section IV(E) of NRC 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 April 22, 2003.
Attachment (I) to this letter provides the requested report. Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, PEK/GT/bjd~
~ ~~~~
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PEK/GT/bjd
Attachment:
(1) 60 Days After Plant Restart Report - NRC Order EA-03-009, Interim Inspection Requirement for Reactor Pressure Vessel Heads at Pressurized Water Reactors cc:
J. Petro, Esquire J. E. Silberg, Esquire Director, Project Directorate I-1, NRC G. S. Vissing, NRC H. J. Miller, NRC Resident Inspector, NRC R. I. McLean, DNR
o
ATTACIMENT (1) 60 DAYS AFTER PLANT RESTART REPORT NRC ORDER EA-03-009, INTERIM INSPECTION REQUIREMENT FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS Calvert Cliffs Nuclear Power Plant, Inc.
June 3, 2003
ATTACHMENT (1) 60 DAYS AFTER PLANT RESTART REPORT -
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 NRC Order EA-03-009 (Reference 1), as modified by Reference (2), and returned the plant to operation on April 22, 2003.
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), AND (b)
Either:
(i)
Ultrasonic testing of each RPV head penetration nozzle (i.e., nozzle base material) from two inches above the J-groove weld to the bottom of the nozzle and an assessment to determine if leakage has occurred into the interference fit zone, OR (ii)
Eddy current testing or dye penetrant testing of the wetted surface of each J-groove weld and the RPV head penetration nozzle base material to at least two inches above the J-groove weld.
Calvert Cliffs requested and was granted relaxation from the requirements to examine the nozzle from the bottom of the nozzle to two inches above the J-groove weld (Reference 2). The relaxation provided the alternative scope of inspecting the nozzles from 0.56 inches above the bottom of the nozzle to a minimum of 0.95 inches above the J-groove weld.
The bare metal visual examination was accomplished with no indications of leakage. Every penetration was examined 360° around. The head was very 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 tvo 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 was performed using an ultrasonic technique. There was no evidence of leakage.
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 a penetrant examination (PT) of the J-groove weld surface.
The initial PT exam revealed small rounded indications that were attributed to fabrication induced artifacts. The indications were removed using a burring tool. The weld surface was PT tested again.
Several very small indications were noted in locations different from the original indications.
These were small enough to be noted as non-relevant and were prototypical porosity indications. A flapper wheel was used to further interrogate these indications. A final PT test revealed no relevant indications. None of the indications noted in the PT exams had characteristics that could have represented a leak path.
All of the control element drive mechanism penetrations were inspected using UT techniques.
The assessment to determine if leakage has occurred into the interference fit zone was performed using an 1
ATTACHMENT (1) 60 DAYS AFTER PLANT RESTART REPORT -
NRC ORDER EA-03-009, INTERIM INSPECTION REQUIREMENT FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS ultrasonic technique. All nozzles were examined from 0.56 inches above the bottom of the nozzle to a minimum of 0.95 inches above the J-groove weld. The majority of the nozzles were inspected to a distance significantly greater than 0.95 inches above the J-groove weld 3600 around. Even those nozzles where the minimum distance above the J-groove weld approached 0.95 inches in one area the majority of the nozzle was inspected to a distance significantly greater than 0.95 inches above the J-groove weld. No indications of degradation, cracking or leaking were identified. Results of the RPV head penetration examinations are provided in Table 1.
REFERENCES:
(1)
Letter from Mr. S. J. Collins (NRC) to Holders of Licenses for Operating Pressurized Water Reactors, dated February 11, 2003, Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors (EA-03-009)
(2)
Letter from Mr. S. A. Richards (NRC) to Mr. P. E. Katz (CCNPP), dated April 18, 2003, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 - Relaxation of the Requirements of Order (EA-03-009), Regarding Reactor Pressure Vessel Head Inspections (TAC Nos. MB7752 and MB7753) 2
ATTACHMENT (1) 60 DAYS AFTER PLANT RESTART REPORT -
NRC ORDER EA-03-009, INTERIM INSPECTION REQUIREMENT FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS TABLE 1 RESULTS OF THE RPV HEAD PENETRATION EXAMINATIONS FOR CCNPP UNIT 2 (Page 1 of 3)
Extent of UT Coverage in Reactor Vessel Head Penetration Nozzle M
Materaae
_____MtrilLeak Path UT Indications/
Mitn Coverage Coverage Weld Below Assessment Leakage Path Pen #
D Above Weld
@ Weld Region Weld Determination Indications PWeeod RooWta)
Root Coverage Coverage Possible?
(Yes/No)
Root (Thet (Theta)
(Theta)
(Theta) 1 2.0 360 360 360 360 Yes No 2
1.6*
360 360 360 360 Yes No 3
1.55*
360 360 360 360 Yes No 4
1.85*
360 360 360 360 Yes No 5
1.65*
360 360 360 360 Yes No 6
2.11 360 360 360 360 Yes No 7
1.40*
360 360 360 360 Yes No 8
1.83*
360 360 360 360 Yes No 9
1.4*
360 360 360 360 Yes No 10 1.e40
- 360 360 360 360 Yes No 11 1.9*
360 360 360 360 Yes No 1 2 1.7*
360 360 360 360 Yes No 13 1.45*
360 360 360 360 Yes No 14 1.95*
360 360 360 360 Yes No 15 1.70*
360 360 360 360 Yes No 16 1.8*
360 360 360 360 Yes No 1 7 2.12 360 360 360 360 Yes No 18 1.45*
360 360 360 360 Yes No 19 1.45*
360 360 360 360 Yes No 20 1.45*
360 360 360 360 Yes No 21 1.55*
360 360 360 360 Yes No 22 1.65*
360 360 360 360 Yes No 23 1.45*
360 360 360 360 Yes No 24 1.7*
360 360 360 360 Yes No 25 1.65*
360 360 360 360 Yes No 26 1.55*
360 360 360 360 Yes No 27 1.46*
360 360 360 360 Yes No 28 1.82*
360 360 360 360 Yes No 29 1.82*
360 360 360 360 Yes No 30 1.75*
360 360 360 360 Yes No 31 1.20*
360 360 360 360 Yes No 32 1.5*
360 360 360 360 Yes No 33 1.24*
360 360 360 360 Yes No 34 1.43*
360 360 360 360 Yes No 35 1.3*
360 360 360 360 Yes No 36 1.45*
360 360 360 360 1
Yes No 3
ATTACHMENT (1) 60 DAYS AFTER PLANT RESTART REPORT - NRC ORDER EA-03-009, INTERIM INSPECTION REQUIREMENT FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS TABLE 1 RESULTS OF THE RPV HEAD PENETRATION EXAMINATIONS FOR CCNPP UNIT 2 (Page 2 of 3)
Extent of UT Coverage in Reactor Vessel Head Penetration Nozzle Material M* Covera terag Weld Leak Path UT Indications/
Min Coverage Coverage Weld Below Assessment Leakage Path Distance Above
@ Weld Region Weld Determination Indications Welde Roeot Root Coverage Coverage Possible?
(Yes/No)
Root (Theta)
(Theta)
(Theta)
(Theta) 37 1.85*
360 360 360 360 Yes No 38 1.30*
360 360 360 360 Yes No 39 1.39*
360 360 360 360 Yes No 40 1.37*
360 360 360 360 Yes No 41 1.2*
360 360 360 360 Yes No 42 1.2*
360 360 360 360 Yes No 43 0.95*
360 360 360 360 Yes No 44 1.05*
360 360 360 360 Yes No 45 1.4*
360 360 360 360 Yes No 46 1.3*
360 360 360 360 Yes No 47 1.15*
360 360 360 360 Yes No 48 1.50*
360 360 360 360 Yes No 49 1.15*
360 360 360 360 Yes No 50 1.2*
360 360 360 360 Yes No 51 1.0*
360 360 360 360 Yes No 52 1.3*
360 360 360 360 Yes No 53 1.2*
360 360 360 360 Yes No 54 1.2*
360 360 360 360 Yes No 55 1.55*
360 360 360 360 Yes No 56 1.80*
360 360 360 360 Yes No 57 1.2*
360 360 360 360 Yes No 58 1.25*
360 360 360 360 Yes No 59 1.55*
360 360 360 360 Yes No 60 1.2*
360 360 360 360 Yes No 61 1.0*
360 360 360 360 Yes No 62 1.25*
360 360 360 360 Yes No 63 1.25*
360 360 360 360 Yes No 64 1.35*
360 360 360 360 Yes No 65 1.50*
360 360 360 360 Yes No ICI
>2 360 360 360 360 Yes No ICI2
>2 360 360 360 360 Yes No IC13
>2 360 360 360 360 Yes No 1CI4
>2 360 360 360 360 Yes No ICI5
>2 360 360 360 360 Yes No IC16
>2 360 360 360 360 Yes No IC17
>2 360 360 360 360 Yes No 4
I ATTACHMENT (1) 60 DAYS AFTER PLANT RESTART REPORT -
NRC ORDER EA-03-009, INTERIM INSPECTION REQUIREMENT FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS TABLE 1 RESULTS OF THE RPV HEAD PENETRATION EXAMINATIONS FOR CCNPP UNIT 2 (Page 3 of 3)
Extent of UT Coverage in Reactor Vessel Head Penetration Nozzle Material Leak Path UT Indications/
Min **
Coverage Coverage Weld Below Assessment Leakage Path Pen #
Above Weld
@ Weld Region Weld Determination Indications Weld Root Root Coverage Coverage Possible?
(Yes/No)
Root (Theta)
(Theta)
(Theta)
(Theta)
CI8
>2 360 360 360 360 Yes No Vent
>2 360 360 360 360 Yes***
No line Relaxation from the Order requirement to inspect two inches above the J-groove weld was granted.
Coverage is for nozzle outside diameter. Nozzle inside diameter coverage is 0.43 inches greater for all control element drive mechanism penetrations.
Leak path assessment performed by PT of weld.
5