ML112990914
| ML112990914 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 05/12/1982 |
| From: | Mayer L Northern States Power Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML112990915 | List: |
| References | |
| NUDOCS 8205190155 | |
| Download: ML112990914 (8) | |
Text
REGULATORY*FORMATION DISTRIBUTION S*EM (RIDS)
ACCESSION NBR:8205190155 DUC,DATE: 82/05/12 NOTARIZED: NO FACIL:50-263 Monticello Nuclear Generating Plant, Northern States AUTHNAME AUTHOR AFFILIATION MAYERL,0, Northern States Power Co.
RECIP,NAME RECIPIENT AFFILIATION Office of Nuclear Reactor Regulation, Director DOCKET #
05000263
SUBJECT:
Forwards Revision 3, "Inservice Insp & Testing Program,"
_,6 DISTRIBUTION CODE: A047S zCOPIES RECEIVED:LTR.. ENCL, SIZE:
TITLE: Inservice Inspection/Testing & Related Correspondence NOTES: '/CiYC4A co.O0 RECIPIENT ID CODE/NAME ORB #2 BC COPIES LTTR ENCL 01 7
7 RECIPIENT ID CODE/NAME NRR CHANEYpD COPIES LTTR ENCL 1
0 ELD/HDS1 NRR/DE/MTEB RGN3 EXTERNAL: ACRS NRC PDR NTIS 1
0 D
15 14 1
1 EG FILE 04 1
1 16 02 10 1
10 1
1 1
LPDR NSIC 03 05 TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL INTERNAL:
1 1
1 1
1 1
1 1
25
Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401 Telephone (612) 330-5500 May 12, 1982 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Information Required for NRC Review of Inservice Inspection and Testing Program and Requests for Relief from ASME Code Section XI Requirements Attached you will find 40 copies of Revision 3 to our report entitled, "ASME Code Section XI Inservice Inspection and Testing Program."
This is a revision of our inservice inspection and testing program description and requests for relief submitted to the Commission on March 27, 1981.
The purpose of this revision is to submit for NRC Staff review an update of the Inservice Inspection (ISI) Program necessitated by the 1981 refueling outage examinations and changes to the Inservice Testing (ISI) Program resulting from commitments made during EG&G review of our second ten year inspection interval.
The revision includes editorial corrections, revisions to existing requests for relief, and two additional requests for relief from the requirements of the ASME Code,Section XI, 1977 Edition, through and including the Summer 1978 Addenda.
Basis for changes to the ISI Program, including Request for Relief No.
51, are described in attachment 1 to this letter. Changes to the IST program are summarized as follows: Valves FW-91-1, FW-91-2, HPCI-14, HPCI-31, HPCI-60, HPCI-65,HPCI-71, RCIC-16, RCIC-31, RCIC-57 RCIC-59, and RHR-21 have been deleted from Request for Relief No. 7 and added to the IST Program since they can be exercized on a limited basis when their systems are not required for operation (i.e. cold shutdown).
Planned modification will allow testing of RHR-21. Valves CRD-115 and CRD-138 have been deleted from Request for Relief No. 9. A limited test can be performed on all CRD-115 check valves during cold shutdown. Operability of CRD-138 check valves can be determined only during control rod testing, which is the reason for the new Request for Relief No. 52.
f yooooo 8205190155 920513 PDR ADOCK 05000263 G
NORTAN STATES POWER COM#NY Director of NRR May 12, 1982 Page -2 These revisions are being submitted for NRC Staff review and approval in accordance with the provisions of 10 CFR Part 50, Section 50.55a(g).
Attached is one copy of the Licensing Fee Determination and a check in the amount of $4000.00 as required by 10 CFR Part 170, Section 170.22.
Instructions are provided for entering Revision 3 in the March 27, 1981 report.
Please contact us if you have any questions related to this revision.
L 0 Mayer, PE Manager of Nuclear Support Services LOM/KNC/js cc Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC State of Minnesota (H Baron)
Hartford Insurance (S Tack)
Attachments I
ATTACHMENT 1 This letter is to update the information that we had provided you in our January 20, 1981 letter that helped provide the basis for Request for Re lief's 15, 16, and 19 of our Inservice Inspection Program for the first interval ending June 29, 1981.
(Refer to item I.A. of Safety Evaluation Report on the Monticello Nuclear Generating Plant Inservice Inspection Program dated April 10, 1981.)
In addition, this information provides the basis for Request For Relief No. 16 and,51 of our present 10 year inter val program that was submitted March 27, 1981.
The following information is being provided as the result of our inspec tions during the maintenance outage from October 1981 to January 1982.
I. Reactor Vessel Shell A. Circumferential Welds
- 1. Access was obtained to 6'-8" of circumferential weld VCBB-1 from nozzle opening N1B. We expect to be able to obtain similar access to this weld from nozzle opening NIA. This is the limit of accessibility to circumferential weld VCBB-1.
- 2. Access was obtained to 20'-5" of circumferential weld VCBB-4 from nozzle openings N4A, N4B, N4C and N4D.
The areas of examination through the nozzle openings were 4'-5",
5'-4", 5'-4" and 5'-4" respectively.
This is the limit of accessibility to circumferential weld VCCBB-4.
- 3. Access to circumferential welds VCBB-2 (beltline region) and VCBB-3 was not obtained. The nozzle openings are not located in close enough proximity to allow access to these welds.
B. Longitudinal Welds
- 1. Access was obtained to 9' of longitudinal weld VLAA-2 from nozzle openings N2G and N8B.
(The top 16" of this weld is within the Beltline region.)
The areas of exami nation through the nozzle openings were 5' and 4' re spectively. We expect to be able to obtain similar ac cess to longitudinal weld VLAA-1 from nozzle opening N2G and N8A.
- 2. Access was obtained to 5'-8" each of longitudinal welds VLCB-1 and VLCB-2 from nozzle openings N5A and N5B, re spectively.
- 3. Access was obtained to 4' of longitudinal weld VLDB-1 from above the biological shield.
Page 1 of 3
S.
ATTACHMENT I II. Bottom Head of Reactor Vessel A. Circumferential Welds
- 1. Access was obtainable to 100% of circumferential weld HCAB-1 from under the reactor vessel.
Examina tion was conducted on 2'-6" of the weld, which is equal to 5.6% of the total length of the weld.
B. Meridional Welds
- 1. Access was obtainable to 2'-5" each of meridional welds HMAB-7 and HMAB-8 from under the reactor vessel.
The remaining meridional welds HMAB-1, HMAB-2, HMAB-3, HMAB-4, HMAB-5 and HMAB-6 are accessible to 2'-5" each.
These welds are40% accessible. The remaining 60% of these welds are located above the reactor vessel sup port skirt and between the biological shield, making them unaccessible.
- 2. Access to meridional welds HMAB-9 and HMAB-10 was measured and found that only 2' of each weld is acces sible. The remaining portion of these welds are lo cated between the control rod drive housing configura tions.
III.
Reactor Vessel Stabilizer Brackets Access to the stabilizer brackets was not obtained. Removal of the cover surrounding the stabilizer revealed access of 1 1/2" clearance around the bracket. Visual examination was hampered by ventilation duct work between the drywell wall and reactor vessel.
These brackets are actually not part of the vessel supporting system, but are designed to stabilize the reactor vessel against jet force loadings (LOCA's) and/or seismic loads. The stabi lizer brackets are designed to allow thermal movement without restraint, and therefore there are no loadings at the vessel as the result of operations. Therefore, inspection of these brackets should not be necessary, unless the brackets experience the design loads.
Page 2 of 3
MONTICELLO R TOR WELD
SUMMARY
EXAM CATEGORY B1.11 B-A Circumfer ential B1.12 B-A Longitudi nal B1.21 B-A B1.22 B-A WELD NUMBER VCBB-1 VCBB-2 VCBB-3 VCBB-4 VLAA-1 VLAA-2 VLBA-1 VLBA-2 VLCB-1 VLCB-2 VLDB-1 VLDB-2 LOCATION Elev. 8'-7" Beltline Elev. 30'-6 1/8" Elev. 41'-5 11/16" 27" in Beltline 27" in Beltline 117" in Beltline 117" in Beltline 1150 2850 1500 330 0 HCBB-1 Bottom Head HCBB-2 Top Head HMCB-1 HMCB-2 HMCB-3 HMCB-4 HMCB-5 HMCB-6 HMAB-1 HMAB-2 HMAB-3 HMAB-4 HMAB-5 HMAB-6 HMAB-7 HMAB-8 HMAB-9 HMAB-10 Top Head Top Head Top Head Top Head Top Head Top Head Bottom Head Bottom Head Bottom Head Bottom Head Bottom Head Bottom Head Bottom Head Bottom Head Bottom Head Bottom Head 16" in Beltline Region 11% of longitudinal weld VLAA-1 weld possibily inspectable 2nd Ten Year Interval LENGTH 57' 57' 57' 57' 11' 11' 11' 11' 11' 11' 11' 11' 44' 25' 7'
7' 7'
7' 7'
7' 6'-2" 6'-2" 61'-2" 61'-2" 61-2"1 61-2"'
61-2"1 61-2"1 141-5"1 131-8" ACCESSIBLE LENGTH EXAMINED EXAMINE 6'-8"/6'-8" 11.7 None / None None / None 20'-5"/20'-5" 35.8 SUBTOTAL 47.5
- 9'
/
- 9' / 9'
- 81.8 None / None None /
5'-8"1/5 5'-8"/5 4' /4 41-9"1/4 2'-6"/2 25'/2 7',
7'!
7',
7'!
7'!
7'!
6'-2"/
6'-2"/
6'-2"/
6'-2"/
6'-2"/
6'-2"/
/2
-- /2 2' /
2' /
None
'-8" 51.5
'-8" 51.5 1
36.3
'-9"1 43.1 SUBTOTAL 37.8 1'-6" 5.6 51 100.0 SUBTOTAL 39.9 71 100.0 1.5' 21.4 7'
100.0 7'
100.0 7'
100.0 7'
100.0
.5-40.5
.5' 40.5 SUBTOTAL 34.8 D
REMARKS Examined '81 Inaccessible Inaccessible Examined '81
- Attempt PER.
Examined '81 Inaccessible Inaccessible Examined '81 Examined '81 Examined '81 Examined '81 Examined '81 Examined "75 Examined '75 Examined '74 Examined '75 Examined '81 Examined '75 Examined '81
- Do PER. 1
- Do PER. 2
- Do PER. 2
- Do PER. 3
- Do PER. 3
- Do PER. 1 Examined '81 Examined '81
- Do PER. 1
- Do PER. 3
& 2, 3% of Beltline Region Circumferential & Longitudinal 3
0 H
IV 0
F
To:
Director of Nuclear eactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 Date:
- Aay 12, 1982 Licensing Fee Determination Fee Type:
Facility License Amendment ____
Materials License Application Other (Description Required Approval y
Materials License Renewal Licensee:
Northern States Power Company Plant:
Monticello Nuclear Generating Plant Docket No. 50-263 50-License No. DPR-22 DPR-Materials License No.
Date and subject of Licensing Request:
Information Required For NRC Review of Inservice Inspection and Testing Program and Requests for Relief from ASME Code Section XI Requirements.
License Amendment or Approval C C
Materials License Category:
lass:
III Fee: $4,000.00
'lass:
Fee:
Fee:
Total Fee Enclosed: $4,000.00 Basis for determination of fee class:
This is a revision of the Monticello Nuclear Generating Plant ASME Code Section XI Inservice Inspection and Testing Plant.
It is being submitted in accordance with 10 CFR Part 50, Section 50.55a(g)(5).
Commission review of Code requirements we have found to be impractical is required.
This is a required approval involving a single safety issue.
Standards of acceptability have been clearly identified by NRC Staff positions.
Prepared by:
Nuclear Support Services Department Northern States Power Company 414 Nicollet Mall -
8th Floor Minneapolis, MN 55401 (612) 330-6763 cc:
NSS File U
)
b*
9 May 12, 1982 Revision No. 3 to Monticello Nuclear Generating Plant ASME Code Section XI Inservice Inspection and Testing Program, dated March 27, 1981 Remove the Following Pages cover i 1u 1-2 through 1-3 1-5 through 1-6 1-8 through 1-9 1-21 through 1-23 1-25 t 1-27 through 1-28 1-33 1-39 1-44 through 1-45 1-49 through 1-53 through 1-56 1-5 8 1-62--
1-66 2
3-5 3-7 1-50 1-54 3-10 thr gh 3-12 3-14 3-17 through 3-18 3-23 4-1 --
4-8 through 4-9 4-11 4-16 through 4-17 4-19 Insert the Follwoing Revision No. 3 Pages cover i i i 1-2 through 1-3 1-5 through 1-6 1-8 through 1-9 1-21 through 1-25 1-27 through 1-28 1 1-39 1-44
(
1-44A (new page) 1-45 t 1-49 through 1-50 1-53 through 1-54 1-56 1-58 1-62 1-66 2-1 3-7 3-10through 3-12 3-14 t
-1 3-17 through 3-18 3-23 u
4-1 4-8 through 4-9 4-11 4-16 through 4-17 (deleted) 4-39 (new page) 4-40 (new page.
Use the "Record of Revisions", page iii, to verify your copy of the program manual is complete and up-to-date following entry of this revision.