ML19347E875

Forwards Addl Info on Corrosion Engineering in Response to NRC 810410 & 14 Ltrs Re FSAR Review.Clarification of Secondary Water Chemistry Control & Monitoring Programs Provided

ML19347E875
Person / Time
Site:	Wolf Creek, Callaway
Issue date:	05/08/1981
From:	Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM
To:	Harold Denton Office of Nuclear Reactor Regulation
References
SLNRC-81-28, NUDOCS 8105140142
Download: ML19347E875 (4)

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May 8, 1981 SLNRC 81 28 FILE: 0541 SUBJ: SNUPPS FSAR - NRC Request for Additional Information Mr. Harold R. Oe'nton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Connission Washington, D.C.

20555 Docket Nos. STN 50-482, STN 50-483, and STN 50-486 Ref:

1)

NRC (Tedesco) letter to J. K. Bryan, dated April 10, 1981, -

Request for Additional Information for the Review of the Callaway Plant, Unit 1

2) NRC (Tedesco) letter to G. L. Koester, dated April 14, 1981, Request for Additional Information for the Review of the Wolf Creek Plant

Dear Mr. Denton:

The referenced letters requested identical information in the area of corrosion engineering.

The enclosure to this letter provides the requested information and will be incorporated into the next revision to the SNUPPS FSAR.

Verygrulyyours, 4.4%C Nicholas A. Petrick RLS/bds/lla27 Enclosure cc:

J. K. Bryan UE G. L. Koester KGE

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SLNRC 81-28 Page Two bec:

A. C. 'Passwater UE G. P. Rathbun KGE J. H. Smith B

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Enclosura to SINRC 81-28 l

282.0 282.1 Tb evaluate the empatibility of the ccntrol rod drive struc-4.5.1 tural materials with *he reactor coolant water, provide the list of materials and specificaticos which are used fcr each ccmpcnent of the control rod drive mechanism. We information in the FSAR does not adequately identify the materials.

Respcnse The requested information is located in Table 5.2-2.

282.2 Provide the following cn your seccndary water chmistry ccntrol 10.3.5 and monitoring progr as:

1.

Sepling schedule for the critical par meters and of control points for these parmeters for the cold startup mode of operaticn:

2.

Procedures used to measure the values of the critical par-neters:

3.

Procedure for recording and management of data:

4.

Procedures defining ccrrective acticns* for off-ccntrol point chemistry conditions: and

- 5.

A procedure identifying (a) the authority respcnsible for the interpretaticn of the data and (b) the sequence and timing of administrative events required to initiate cor-rective action.

Verify that the stem generator secondary water chemistry ccn-trol progrm incorporates technical recmmendations of the NSSS.

Any significant deviations frcm NSSS reccmmendaticrs should be noted and justified technically.

• Branch Technical Positicn MIEB 5-3 describes the acceptable means for mcnitoring seccndary side water chemistry in IMR ste m generators, including corrective actions for off-ccntrol point chmistry conditions. However, the Staff is amenable to alternatives, particularly to Branch Technical Positicn B.3.b(9) of MrEB 5-3 (96 - hcur time limit to repair or plug ccnfirmed ccndenser tube leaks).

Response

1.

We ccntrol point for each stem generator is the respective ste m generator bicsdcwn. We critical parmeters for the cold startup mode cf cperation are free hydroxide, caticn conductivity and pl. These parameters will be sapled five times a week for each ste m generator. W e feedwater, stem,

and ccndensate will be sapled three times a week.

Enclosure to SLNRC 81-28 Page Two 2.

Analytical chenistry procedures will be used in the labora-tory to measure the critical paraneters. R ese procedures have been developed utilizing ASIM, Standard Methcds, and manufacturer equipnent manuals.

3.

An administrative denistry procedure will provide guidance for. recordirq and management cf data. Genistry data fran the lab will be subnitted to the Plant Chmist for interpre-taticn and reviewed by the Assistant Superintendent Engineer-ing-Radiochenistry.

4.

We Radiaticn Chenistry Department will provide current chemistry conditions with reccamendations to the Operations Depctment for corrective acticn. Corrective actions will be performed by the Operaticos Department.

5.

An administrative denistry procedure identifies the authcr-ity respcnsible for interpretatica of data as the Radiaticn Genical Forenan, the Plant Chenist, and the Assistant Superintendent Engineering-Radiochenistry.

'Ihe sequence of administrative events required to initiate corrective action is delineated as follows:

Plant Rad-Chen Rad-Chen Tech Forenan

, Genist I

v v

v Operating Asst. Supt. Eng.

Supervisor Radiochenistry Iv Corrective Acticn Please note that the personnel and organizaticnal titles used above are applicable to Callaway. Similar positicns, but different titles, apply to Wolf Creek.

Se stean generator seccndary water chenistry ccntrol program incor-porates the technical reconmendaticos of Westinghouse.

AJ stated in FSAR Secticn 10.3.5.1, the requirements of MPEB 5-3 are met.