ML20101U034

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Forwards Repts of CRD Operability Evaluation,Refurbishment Program,Maint Program,Surveillance & Operating Procedures
ML20101U034
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 01/31/1985
From: Gahm J
PUBLIC SERVICE CO. OF COLORADO
To: Martin R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20101U035 List:
References
P-85040, NUDOCS 8502060539
Download: ML20101U034 (2)


Text

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d public Service Company *f OcEomde 16805 WCR 19 1/2, Platteville, Colorado 80651 January 31, 1985 Fort St. Vrain Unit #1 P-85040

  • M@MDMM %

Mr. Robert Martin, Regional Administrator i

FEB - 1125 U. S. Nuclear Regulatory Commission 611 Ryan Plaza, Suite 1000 y

Arlington, Texas 76011 Attention: Mr. E. H. Johnson

SUBJECT:

Submittal of Various CRD0A Related Reports

REFERENCES:

(1) PSC Letter, Lee to NRC RIV Regional Administrator, dated 1/4/85 (P-85003)

(2) NRC Letter, Martin to Lee, dated 1/17/85 (G-85024)

(3) PSC Letter, Lee to NRC RIV Regional Administrator dated 1/28/85 (P-85030)

Dear Mr. Martin:

In response to commitments made in the referenced letters, Public Service Company of Colorado submits the attached reports and procedures for Nuclear Regulatory Commission review. The attachments are summarized as follows: - Control Rod System Operability Evaluation Repor,t - Control Rod Drive and Orificing Assembly Refurbishment Program Report - Control Rod Drive and Orificing Assembly Proposed Preventive / Predictive Maintenance Program Report - Control Rod Drive and Orificing Assembly Refurbishment Program Radioactive Waste Handling Analysis Report - Control Rod Drive and Orificing Assembly Interim Surveillance Program Report l-l0 6 1

pupf) OtiQi n L Q k\\V 8502060539 850131 PDR ADOCK 05000267 1

P PDR L

A g

-g- - Wattmeter Use.to -Determine Inserted Absorber String Position Report - Exerpt from Issue.15 of -SOP 12-01 describing operator actions to prevent overdriving of control rods'past the rod-in limit. '-' Operations Order No. 84-17 describing operator actions upon a loss of purge flow and/or detection of high moisture levels in the primary coolant. - Current CR0 Temperature Data Collection procedure which requires Station Manager notification upon discovery of a measured CRD temperature in excess'-

of 250 F.

If you have any questions or comments regarding these documents, please contact Mr. Mike Holmes at (303) 571-8409.

Sincerely, b

e J. W. Gahm Manager, Nuclear Production-Fort St. Vrain Nuclear Generating Station JWG:FJN/alk ~

Attachments E