ML20024G216
| ML20024G216 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 09/19/1977 |
| From: | Wachter L NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20024G212 | List: |
| References | |
| A00L-770919, AL-770919, NUDOCS 9102080348 | |
| Download: ML20024G216 (4) | |
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3 UNITED STATES NUCLCAR REGUIATORY COMMISSION 1
}i NORDIERN SIATES POWER COMPANY MONTICELLO NUCLEAR GENERATING P1 ANT q l Locket No. 50 263 gj.l
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REQUEST FOR AMENTHENT TO OPERATING LICENSE NO. DPR-22 1
(License Amendment Request Dated September 19, 1977)
Northern States Power Company, a Minnesota corporation, requests authorization for changes to the Technical Specifications as shos.m on the attachments labeled Exhibit A and Exhibit B.
Exhibit A describes the proposed changes along with reasons for the change.
Ex.hibit B is a set of Technical :>pecification pages incorporating the proposed changes.
This request contains no restricted or other defense information.
NORTHERN STATES POWER COMPANY NOM M By O L J Wachter i
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Vice President, Power Production 6 i
System Operation On this 19th day of September 1977, be fore en a notary public in and for said County, personally appeared L J Wachter, "i ce President, Power Production & System Operation, and first being duly sworn i
acknowledged that he is authorized to execute this document in behalf of Northem States Power Coopany, that he knows the contents therect and that to the best of his knowledge, information and belief, the statementt rade in it are true and that it is not interposed for delay.
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.1i EXHIBIT A 0
hl 10NTICELID NUCLEAR GENERATING PIANT f)
DOCKET NO. 50-263 4
s License Amendment Request Dated September 19, 1977
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Proposed Changes to the Technical Specifications, Appendix A t'
of Provisional Operating License DPR-22 tj Pursuant to 10 CFR 50, Section 50.59, the holders of Provisional Operating g
License DPR-22 hereby propose the following change to Appendix A, Technical
'J Specifications:
}l Table 4.6.1. "In-Service Inspection Requirements for Monticello" i!
PROPOSED CHANGE
- a. Change the examination method for category E(2) on page 125 frca volumetric to pressure tests.
- b. Add a new note at the end of Table 4.6.1 as follows:
- 1. The specified inspection interval end extent of examination are nominal values only.
Inservice inspection may be performed during normal plant outages such as refueling shutdowns or maintenance shutdowns occurring during the inspection interval.
Except where it is stated that. examinations may be deferred to the end of the inspection interval, at least 25% of the required examination shall have been completed by the expiration of one-third of the inspection interval (with credit for no more than 33-1/3% if additional examinations are completed) and at least 50% shall have been completed by the expiration of two-thirds of the inspection interval (with credit for no 4
more than 66-2/3%). The remaining required examinations shall be completed by the end of the inspection interval.
y Inspection intervals may be extended by as much as one year O
to permit inspections to be concurrent with plant outages.
REASON FOR CHANGE These changes are requested on an interim basis until our License Amendmen',
Requent dated August 30, 1977 has been reviewed and approved by the Ccarais-sion. Our August 30, 1977 submittal requested the removal of Table 4.6.1 and required inservice inspection and testing to confom to the requirements of 10 CFR 50, Section 50.55a(g).
1 Change (a) substitutes examination during system pressure tests for a volumetric examination. Based on Section II of the ASME Code (1974 Edition with Addenda through Sumer 1975), control rod housing pressure boundary welds are Table IWB-2500 Examination Category B-P.
They are exempted from volumetric and surface examination by Article IWB-1220(b)(1).
Examination during system pressure tests is specified for these components. The requirement for I
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EXHIBIT A 3
, j a volumetric inspcction was contained in a preliminary version of the AS)E inservice inspection requirements when Table 4.6.1 was drafted.
Section XI of the ASME Code had not yet been issued. ne 1970 and subsequent editions of the Code have not specified volumetric examination for these components.
Volumetric inspections have been conducted over the last six years at great expense. Wey have been time consuming, difficult to coordinate
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with other outage activities, and have resulted in significant occupational
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radiation exposures. Thermal sleeves removed to perform the volumetric inspection must frequently be renewed. Thermal sleeves that that would be needed for anticipated replaceent if volumetric inspection was per-formed this outage have not been available. A significant delay in return to service could result tf we must perform the volumetric inspec-tion and replacement thermal sleeves cannot readily be found.
We have been informed by our reactor vendor that Monticello is the only BWR known to have a Technical Specification requirement for volumetric inspection of these components.
Change (b) is being submitted following discussions with our licensing project manager. Table 4.6.1 has always been liberally interpreted and specified inspection intervals have been adjusted to conform to refueling outages.
Be majority of. the specified inspections can only be performed during refueling.
he specified intervals in the " Inspection Interval" column and the " Extent of Examination" column cannot be strictly adhered to.
The requested change adds a new page to the table with a note that indicates intervals may be adjusted to be concurrent with plant outages. This note is consistent with the requirements of 10 CFR 50, Section 50.55a(g). We note simply states the degree of flexibility now permitted by Section XI of the ASME Code.
Strict conformance to Table 4.6.1 would necessitate frequent shutdowns for inservice inspection to comply with an arbitrary inspection schedule.
l SAFETY EVAIEATION The requested changes are consistent with the requirements of 10 CFR 50, Section 50.55a(g) and Section XI of the ASME Code (1974 Edition with l
Addenda through Summer 1975). Change (a) replaces one inspection method with a completely satisfactory alternate method. Change (b) revises the-table specifying inservice inspection intervals to i
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include the ASME Code allcwable flexibility in scheduling inspections.
There are no nuclear safety implications.
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l1 EXHIBIT B License Amendment Request Dated September 19 1977
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'Ihis exhibit consists of the following pages revised to incorporate the proposed ij Technical-Specification changes:
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Page 125 129A (new page)
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