ML20033B218

Forwards Request for Addl Info Re Chemical Engineering for Response by 811130

ML20033B218
Person / Time
Site:	Perry
Issue date:	10/30/1981
From:	Houston M Office of Nuclear Reactor Regulation
To:	Davidson D CLEVELAND ELECTRIC ILLUMINATING CO.
References
NUDOCS 8112010056
Download: ML20033B218 (4)

Text

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OCT 3-01981 sy/,

Docket Hos. 50-440

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'O and 50-441

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'h'rty Mr. Dalwyn R. Davidson

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J Vice President - Engineering 4

The Cleveland Electric Illuminating Company m

Post Office Box 5000 Cleveland, Ohio 44101

Subject:

Request for Additional Information - Chemical Engineering In the perfonaance of the Perry licensing review, the staff has identified

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concerns in regard to chemical engineering. The information that we require is identified in the enclosure.

We request that you provide the information not later than ilovember 30, 1931.

If you require any clarification of the request, please contact 4

me at 301-492-8430.

Sincerely, IS{

M. Dean Houston, Project Manager Licensing Branch tio. 2 Division of Licensing

Enclosure:

Distribution:

bcc:

Request for Additional Docket File ilPC PDR Information LB#2 Local PDR DEisenhut/RPurple ilSIC cc w/ enclosure:

RTedesco TERA See next page ASchwencer TIC DHouston ACRS (16) itService I&E (3)

OELD 8112010056 011030 PDR ADOCK 05000440 A

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Mr. Dalwyn R. Davidson 007.9 0 1981 Vice President, Engineering The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101 cc: Gerald Charnoff, Esq.

Shaw, Pittman, Potts & Trowbridge 1800 M Street, N. W.

Washington, D. C. 20006 Donald H. Hauser, Esq.

The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101 Resident Inspector's Office U.S.N.R.C.

Parmly at Center Road Perry, Ohio 44081 Donald T. Ezzone, Esq.

Assistant Prosecuting Attorney 105 Main Street Lake County Amninistration Center Painesville, Ohio 44077 Tod J. Kenney 228 South College, Apt. A Bowling Green, Ohio 43402 Daniel D. Wilt Wegman, Hesiler & Vanderberg 7301 Chippewa Road, Suite 102 Brecksville, Ohio 44141 Robert Alexander 0CRE Interim Representative 2030 Portsmouth Street Suite 2 Houston Texas 77098 Terry Lodge, Esq.

915 Spitzer Building Toledo, Ohio 43604

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ADDITIONAL INFORMATION REQUIRED BY-CHEMICAL ENGINEERING BRANCH FleM

' PERRY NUCLEAR POWER PLANT UNIT NOS.1 & 2 Cleveland Electric Illuminating Company

~281.1 Verify that provisions have been made for draining and. venting. reactor. water (5.4.8)'

cleanup system components through a closed system in accordance with GDC 60' and 61.

281.2 Verify that the initial total capacity of new demineralizer resins (conden.

(5.4.8) sate and primary coolant) will be measumd.

Describe the method to be used

( 10. 4.6) for this measurement (Regulatory Position C.3 of Regulatory Guide 1.56, Revision 1).

281.3 The. reactor coolant limits and corrective action to be taken if the conduc-(5.4.8) tivity, pH, or chloride content is exceeded will be utablished in the Tech-(10.4.6) nical Specifications.

Describe the chemical analysis methofs to be used for their detemination (Regulatory Position C.6 of Regulatory Gu.ide 1.56, Revi-sion 1).

281.4 Describe-the water chemistry control program to assure maintenance of con-(10.4.6) densate demineralizer influent and effluent conductivity within the limits of Table 2 of Regulatory Guide 1.56, Revision 1.

Include conductivity, meter

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alam set points and the corrective action to be taken if the limits of Table 2 are exceeded.

281.5 In accordance with Position C.1 of Regulatory Guide 1.56, Revision 1, des-(10.4.6) cribe the sampling frequency, chemical analyses, and established limits for.

purified condensate dissolved and suspended solids that will be perfomed j

and the basis for these limits.

l 281.6 a.

Indicate the total amount of paint or protective coatings (area and film (6.1.2) thickness) used inside containment that do not meet the requirements of ANSI N101.2 (1972) and Regulatory Guide 1.54.

We will use the above infomation to estimate the rate of combustible gas generation vs. time l

and the amount (volume) of solid debris that can be fomed from these unqualified organic materials under DBA conditions that can potentially reach the containment sump. A G value of 5 will be used unless a lower G value is justified technically.

b.

In order for the staff to estimate the rate of combustible gas genera--

tion vs. time due to exposure of organic cable insulation to ~ DBA condi-tions inside containment, provide the following information:

I 1)

The approximate total quantity (weight and volume) of organic cable insulation material used inside containment, including i

l uncovered cable and cable in closed metal conduit or closed cable tr ays. We will give credit for beta radiation shielding for cable in closed conduit or trays if information is provided as to the respective quantities of cable in closed conduits I

or trays vs. uncovered cable.

2) The approximate breakdown of cable diameters and. conductor or cross section associated or an equivalent cable diameter and l

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- conductor cross section which is representative of the total cable surface area consistent with the quantity of cable sur t face area consistent with the quantity of cable identified in

1) above.

3) The major organic polymer or plastic material associated with the cable in 1) above.

If this information is not provided, we will assume the cable insulation to be polyethylene and a G value of 3.

281.7 Regarding the Spent Fuel Pool Cleanup System, provide the following infor-(9.1.3) mation:

Describe the samples and instrumentation and their frequency of measure-ment that will be performed to monitor the Spent Fuel Pool water purity and need for ion exchanger resin and filter replacement. State the radio-chemical limits to be used in monitoring the spent fuel pool water and for initiating corrective action.

Provide the basis for establishing these limi ts. Your response should consider variables such as: gross gama and iodine activity, demineralizer decontamination factor, and crud ~ level.

I 281.8 Acceptance Criterion 2.g in Standard Review Plan S'ection 9.3.2 states that (9.3.2) passive flow restrictions to limit reactor coolant loss from a rupture of the sample line should be provided.

You do not address this criterion in the FS AR.

Describe how the requirement of maintaining radiation exposures to as low as is reasonably achievable will be met in the event of a rupture of the sample line containing contaminated primary coolant, in accordance with Regulatory Position C.2.i(6) of Regulatory Guide 8.8, Revision 3 (June 1978).

281.9 Acceptance criterion 1.b in Standard Review Plan Section 9.3.2 indica'tes (9.3.2) that atmosphere and sumps inside containment should be sampled.

Describe provisions to sample inside the containment in accordance with the require-nents of General Design Criterion 64 in Appendix A to 10 CFR Part 50 and Regulatory Guide 1.97, Revision 2.

281.10 Provide information that satisfies the attached proposed license conditions (TMI for post-accident sampling.

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