ML18348A702

Letter ASLB Prairie Island Hearings

ML18348A702
Person / Time
Site:	Palisades
Issue date:	03/31/1977
From:	Hoffman D Consumers Power Co
To:	Schwencer A Office of Nuclear Reactor Regulation
References
Download: ML18348A702 (3)

Text

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~@rn1ll ~ @1 ITTJW General Offices: 212 West Michigan Avenue. Jackson, Michigan 49201

• Area Code 517 788-0550 March 31, 1977 REGUlATDRY Dilt'J{[T All CDPY_

Director of Nuclear Reactor Regulation Att:

Mr Albert Schwencer, Chief Operating Reactor Branch No l US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - ASLB PRAIRIE ISLAND HEARINGS In response to a request telecopied to us on March 17, 1977 for information related to the Palisades Plant steam generator operating experience, the at-tached Table I was provided by telecopy on March 21, 1977.

The following submittals should also be referenced for more detail relating to Palisades steam generator operating history:

Date 1-29-73 3-6-73 7-23-73 8-8-73 9-21-73 12-21-73 1-15-74 1-29-74 2-15-74 3-20-74 3-27-74 6-14-74 6-26-74 7-5-74 7-9-74 7-22-74 7-26-74 8-1-74 8-20-74 8-28-74 11-7-74 12-13-74 First SG Leak Results of Repairs to SG Leakage on SG Leakage From B-SG Title Schedule of Activities During SG Repairs Update on SG Repairs Requesting Withholding Information Nonproprietary Information on SG for Public Document Room CEN-2 (P) SG Report (Proprietary)

More Information on SG Tube Exam/Report Further Information on SG Tests and Numerical Value for Fatigue Endurance Limit A0-10-74 Re SG Primary-to-Secondary Leakage on May 5, 1974 More Information on A0-10-74 SG Status Report Eddy Current Inspection - Preliminary Report Battelle Report - Tube Plugging Criteria Corrected Page to Eliminate CE Proprietary Information Status of SG Repairs Technical Specifications Change Request Request to Operate Plant at Certain Levels Conclusion of Flushing Report Technical Specifications Change Request - Augmented Inservice Inspection Program for SG

,,,,...--... \\..

2 Date 1-3-75 1-31-75 2-6-75 3-10-75 3-25-75 6-24-75 8-5-75 8-6-75 8-14-75 2-12-76 2-17-76 3-1-76 3-9-76 3-12-76 3-18-76 3-22-76 3-22-76 4-6-76 12-22-76 David P Hoffman Title Eddy Current Testing During December 1974 "A" SG Additional Information With Regard to the "Palisades Plant

'A' SG Eddy Current Testing - December 197_4 '.'.... __......

Comparison Data Taken in JlUle 1975 Versus Data Taken in December 1974 Eddy Current Inspection of Palisades SG and Technical Specifications Change Additional Eddy Current Test Results Results of an Overcheck Performed on the February 1975 Eddy Current Proposed Technical Specifications Change, Steam Generators Inspection Interval Extension Correction to Proposed Technical Specifications Change Submitted 8-5-75 Correction to 8-5-75 Letter Requesting Steam Generator Inspection Interval Extension Report on "Analysis to Determine Allowable Tube Wall Degrada-tion for Palisades SG" SG Flushing Report Number 13 for Palisades Plant Tube Burst and Leakage Test Report March 1976 ECT Report and Technical Specifications Change Notice of Issuance of Amendment to Provisional Operating License Tube Wall Degradation Analysis Questions Corrections to March 1976 ECT Report Corrections to Tube Wall Degradation Analysis Corrections to Tube Wall Degradation Analysis CENC-42 (P) SG Tube Repair Sleeving Assistant Nuclear Licensing Administrator CC:

JGKeppler, USNRC

TABLE I CONSUMERS POWER COMPANY PALISADES PLANT Docket No. 50-255 License No. DPR-20

a. Significant operating history

1.

OL date -

3-24-71 (12-31-71 First P.ower)

2. Full power operation -

First Achieved - April 1973

3. Major period(s) of downtime (nonrefuelin.g) - 2 Years for S/G _Repairs

b. Materials of construction for major secondary system components

1.

SG tubes -

Inconel 600

.._,..----------..,,,..,.--..,,..-------------------------------------~

2.

SG tube sheet -

Carbon Steel

-=---------,,,-~--"="'"--.,,.----------------------------~

3.

SG tube support plates -

~c.,,..a.... rb_o_n_,..s.,,..t....,e,...e_l_,,...,_....,,,.....,..._-:-:,...---...,,.,,,,....,,-=---=-:=':"'----

4.

Condenser tubes -

Originally... Admiralty; Currently 10 CuNi

5. Other - --------------------------------------------------------

c. Operational history of secondary water treatment d *

1. Period of use of phosphates -

12/71 Through 8/74

2. Period of use of AVT -

Since ""'9...,7=7-1--4..:..,_...;;;... _ __::::_....1.-:__ __________

3. Period of use of condensate demine~alization -

None

4.

Other -

Condenser cooling water - typical chemical composition Closed Cycle Mechanical Draft Sodium (Na) - 20 ppm Calcium (Ca) - 125 ppm Magnesium (Mg) ".' 35 ppm Cooling Towers Conductivity - 800 mmhos ph - 7.7 to 8.o

'M' Alkalinity - 80

e. History of significant condenser tube leakage Condenser Retubed in Late 1974 (Finished 12/74)

1. Date discovered -

Nine Occasions Since July 1976

2.

How discovered -

Sodium Analyzer and S/G Blowdown Analysis (Na+, ca+, Mg++)

3.

Leakage associated - --------------------------------------------

f. Denting history

1. Date discovered -

February 1976

-=~--,,,_-----=:...;.....,--....,..,..-----------------------------~

2.

How discovered -

Eddy Current Testing

3.

Leakage associated (gpm) -

None

g.

Steam Generator Tube plugging history

h.

1. Dates -

2/73, 8/73 Thro~gh 8/74, 2/75, 2/76

2.

Number of tubes -

1925 in 11A 11 Steam Generator. 1744 in 11B11 Steam Generator Operating restrictions imposed on the plant due to degraded SG conditions-Only Restrictions InvolvedArethe Increased Frequency of Eddy Current Inspections