ML20205G745
| ML20205G745 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 11/05/1985 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Butcher E Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR P-85387, TAC-11025, TAC-52230, TAC-56302, NUDOCS 8511130328 | |
| Download: ML20205G745 (3) | |
Text
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6 OPublic Service-
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Company of Colorado 2420 W. 26th Avenue, Suite 100D, Denver, Colorado 80211 November 5, 1985 Fort St. Vrain Unit No. 1 P-85387 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Attn: Mr. E. J. Butcher, Jr.
Acting Chief Operating Reactors Branch No. 3 Docket No. 50-267
SUBJECT:
NUREG-0612, Control of Heavy Loads at Nuclear Power Plants
REFERENCES:
- 1) PSC Letter Warembourg to Butcher dated October 15, 1985 (P-85361)
- 2) Telephone Conversation Between PSC & NRC on October 22, 1985 to Discuss FSV Heavy Load Reports
Dear Mr. Butcher:
In Reference 1 above, PSC submitted to the NRC the Phase I Control of Heavy Loads Report.
In Reference 2,
the NRC requested that PSC clarify certain information contained in this report. The following is a listing by report section and additional information which should clarify NRC concerns:
1.
Section 2.1.3 b) Heavy Load Procedure and Change Process The NRC has requested that interim load handling measures be used until the procedures, as comitted to in Reference 1,
can be put into place (anticipated to be April 15, 1986).
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PSC/ will develop and ' implement, interim heavy load
_ handling ' measures for loads. weighing one. ton or-more and
' when - used with the' handling systems listed in Table 2.1.3 - of the. Phase':IsFSV Heavy Load ~ Report.- The. interim measures'
- will not' apply ~ to movements of'the fuel handling machine or
- auxiliary transfer cask.by the reactor' building crane with
. the: snubber. system engaged. The, reasons for this position are discussed in Section 2.2.3 of_ the Phase ~II. FSV Heavy:
- Load LReport,- also ' submitted by Reference 1..The interim-
- measures.will'be implemented prior to further handling of
^
- heavy loads.
- 2.:
Section 2.1.3 a) Drawings or Sketches Sufficient to Clearly Identify the. Location of Safe Load Paths, Spent Fuel, and
- Safety-Related Equipment-It-
- is PSC's intent to limit the need for safe. load paths as much as possible, and to rely upon.the use of
--limiting-heavy load heights. However, safe load paths, if
' found.necessary,~will be appropriately incorporated into plant lead handling procedures by April 15, 1986.
. 3..-
Section12.1.3-d) Lifting Rigs / Devices The modification to.special lifting beam 158D979 is to j
increase the factor of: safety of the beam,(from 3.5 to 5 based' on ultimate-strength of the beam material) to comply with the factor'of safety required-in ANSI N 14.6-1978. PSC does._not' anticipate use_ of the beam for_ heavy load lifts P
until after modifications are complete, anticipated to.be
' April'15 -1986.
4.-
- Section 2.1.3-d) ANSI 14.6-Section 3.2.1~
7
- With respect-to testing of special lifting devices, PSC
- intends to use. periodic.Non Destructive-Examination (NDE) of 4'
load: bearing' welds to comply with -the -intent of
. ANSI N14.6-1978.. NDE-is currently performed by PSC on s'pecial _ lifting _ devices.
5.-
Section 2.1.3 d)' ANSI N14.6-Section 3.2.1
- Calculations-were -performed by Sargent &.Lundy
- Engineers (S&L) to: conclude that-the'special' lifting devices listed- -in Table 2.1.3-2 meet the requirements-of-
Additionally, S&L performed calculations and performed a review of vendor drawings to conclude that the lifting
- devices ' listed ;in' - Table 2.1.3-3 meet the' requirements of
-e ANSI B30.9-1971.
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t Hopefully, the above information will resolve NRC concerns. ~If you..have any questions on this matter, please contact Mr. M.H.~ Holmes at (303) 480-6960.
Very truly yours, b R.1Ym/
D. W. Warembourg, ger Nuclear Engineering Division DW/ RAG:pa -
cc: K. Heitner i
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