ML18079A519

Submits Addl Info Re PWR Feedwater Lines,In Response to 790525 Request

ML18079A519
Person / Time
Site:	Salem
Issue date:	07/02/1979
From:	Schneider F Public Service Enterprise Group
To:	Stello V Office of Nuclear Reactor Regulation
References
NUDOCS 7907110402
Download: ML18079A519 (17)

Text

Frederick W. Schneider Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/430-7373 Vice President Production July 2, 1979 Mr. Victor Stello, Jr.,

U.S. Nuclear Regulatory Commission DirectorlltATORY bOCKET Fil[ COPY Division of Operating Reactors Office of Nuclear Reactor Regulation Washington, D.C. 20555

Dear Mr. Stello:

NRR INFORMATION REQUEST DATED MAY 25, 1979 PWR FEEDWATER LINES NO. 1 UNIT SALEM GENERATING STATION SUPPLEMENTAL RESPONSE Pursuant to our initial response of June 14, 1979, the following supplemental information is hereby submitted for your evaluation:

4. The Code edition for fabrication of feedwater piping within the containment is ANSI B31. 7-1269.

5. There were no fracture toughness requirements imposed on this piping.

Pres*erv'ice/Tnservic*e Tnspection and Operating History Feedwater piping (nuclear class 2) from feedwater stop check valve to Steam Generators No. 11, 12, 13, and 14 were examined, by percentages required,. in accordance with the 1971 Edition, Winter 1972 Addenda o.~_..'

the ASME B&PV Code Section XI. f

Mr. Victor Stello, Jr. 7/2/79 Total Circumferential Welds (Both Fabricator Welds

& Field Welds) Examined Note 11 18 8 Did not examine 14-BF-2111-18 (reducer to nozzle weld) on Loop 11 - weld in question.

12 19 8 Did examine 14-BF-2121-19 (re-ducer to nozzle weld) on Loop 12-weld in question. No UT from nozzle side due to nozzle con-figuration. Three (3) indica-tions resolved as geometry.

13 24 10 Did examine 14-BF-2131-24 (~lbow to nozzle) on Loop 13 - weld in question. No UT from downstream side due to nozzle configur~tion.

Ten (10) indications resolved as root geometry.

14 16 7 Exam did not include 14-BF-2141-16 weld in question.

Item 2 Two BF circumferential welds in Loop 11 were examined during the second ISI (first refueling) outage.

1) 14-BF-2111-3

2) 14-BF-2111-4 Results: 14-BF-2111-3 MT - No indications (special examination)

UT - No examination downstream due to pipe configuration. Two indications resolved as geometric.

14-*BF-2111-4 UT - No examination upstream due to pipe configuration. Seven indications resolved as geometric.

Corrective Action: None required.

Mr. Victor Stello, Jr. 7/2/79 Item 3 Four BF circumferential welds are scheduled for examination during the first ISI Interval (7/1/79 to 6/30/81). One examination (14-BF-2111-4) has been completed for ISI. One examination (14-BF-2111-3) has been completed as a supplemental exam for investigation of heat treatment results during construction.

Presently scheduled per ten year plan:

14-BF-2111-4 Completed Second Outage 1979 14-BF-2121-16 Scheduled 1982 Outage 14-BF-2131-19 Scheduled 1985 Outage 14-BF-2141-3 Scheduled 1985 Outage NOTE As a result of the General Manager,and NRC letters referenced, the following welds have been examined:

llBF Loop 14-BF-2111(18) & 14-BF-2111(17) 12BF Loop 14-BF-2121 (19) & 14-BF-2121 (18) 13BF Loop 14-BF-2131(24) & 14-BF-2131(23) 14BF Loop 14-BF-2141 (16) & 14-BF-2141 (15)

Preliminary Results:

Confirmed indications on 14-BF-2111(18), 14-BF-2131(24),

and 14-BF-2141(161. Suspect indications not resolved on 14-BF-2121()9).

Tt'eni 4 There have been no reports of water hammer occurring since the unit has been in service. The feed rate is limited to increasing steam generator levels to< O. 2% per minute on the wide range if steam genera tor levels are< 10%.

The chemical treatment of the secondary system is the standard AVT control using ammonta and hydrazine. The unit has operated with AVT tre~tme~t d~ring the entire.service period starting late in 1976.

'rh.e. ch.emi.stry specifications are outlined on the attached Westinghouse Taole 7~-2.

We have also attached a typical chemistry log sheet with data taken from the week of March 11, 1979.

Mr. Victor Stello, Jr. 7/2/79 The water chemistry control of Salem No. 1 Unit, since initial com-mercial operation, has been excellent with only minor condenser in-leakage until July 5, 1978. During the next four months condenser leaks were encountered frequently. Immediate corrective action by station personnel maintained the critical parameters within the Westinghouse "Limiting AVT Specifications for Power Operation at Sea or Brackish Water Sites" outlined on the attached Table 7-4.

The dissolved oxygen levels in the condensate system have been beyond the expected limits since the unit was placed in service. An intense program has been in progress over the past several months to resolve this problem.

During the present refueling outage the main condenser is being re-tubed, a full flow condensate polishing system is being installed, and the condenser and associated piping inspected for oxygen in-leakage. When the unit is returned to service, it is anticipated that the completion of these programs will enable the station to be in full compliance with the specified chemistry control.

Sincerely, Attach.

CC: Mr. B. H. Grier NRC, King of Prussia, Pa.

Mr. L. J. Norrholm NRC, Hancocks Bridge, N.J.

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WESTINGHOUSE PROPRIETARY Table 7-4 Limiting AVT Specifications for Power Operations at Sea or Brackish Water Sites Control Parameter Steam Generator Blowdown Two Weeks 24 Hours Immediate

/1 /1 pH @ 25°C *s.o - 9.2 N/A <8.0 or >9.4 Cation Conductivity >2.0 but !_120 N/A >120 J.Jmhos/cm @ 25°C Free Hydroxide >0.15 but <l.O ~1.0 ppm as Caco 3

Blowdown Rate Maximum Available Capacity gpm/SG

• Instrumented Measurement Recommended.

N/A Not Applicable.

Comment: Operation beyond the normal AVT specifications is limited as indicated above. Corrective action including shutdown, if necessary, is recommended within the time periods as applicable.

/1 An increase of 0.4 pH units to the normal control pH ~imit of 9.0 will result from a Free Hydroxide concentration of 1.0 ppm as Caco

• However, 3

pH is not intended to be the Free Hydroxide determinant.

/2 No relief for Free Hydroxide over and above the Normal Operating Control Limit is provided for periods in excess of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

7-18 Revision 1 January, 1975

lllSTt~r.HOU~F PROPRIETAllY

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pH NH, N2H4 CAT.

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1" ~ID REMARKS '

,, @25°C 8.5-9.0 ppm

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