ML20069M286

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Requests Confirmation of Status of Tech Specs Re Inerting. Tech Specs Issued as Exception to 10CFR50.44, Stds for Combustible Gas Control Sys in Lwrs
ML20069M286
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 11/18/1982
From: Schroeder C
COMMONWEALTH EDISON CO.
To: Schwencer A
Office of Nuclear Reactor Regulation
References
5454N, GL-82-17, GL-82-23, NUDOCS 8211230516
Download: ML20069M286 (2)


Text

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Commonwealth ECoon

?

One First National Pt.:ta. ( tago, litenois O

Address Arply to: Post Ofnce Box 767 Chicago, libnois 60690 Novembe r 18, 1982 Mr.

A. Schwence r, Chie f Licensing Branch #2 Division o f Licensing

. U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

LaSalle County Station Unit 1

~

Requirement for Inerting Prima ry Containment f'

s NRC Do cket No. 50-373 References (a):

Generic Le tter 82-17, Inconsistency Between Requirements o f 10 CFR 50.54(t) and Standard Technical Specifications for Performing Audits o f Emergency Preparedness Programs.

(b):

Generic Le tter 82-23, Inconsistency Between Requirements o f 10 CFR 73.40(d) and Standard Technical Specifications for Performing Audits of Safeguards Contingency Plans (Security Plan).

(c):

10 CFR 50.44 Standards for Combustible Gas Control System in Light Water Cooled Power Reactors, Section 50.4 4. (c) (3) (1).

(d):

LaSalle County Station Technical Specification 3.6.6.2, Drywell and Suppression Chamber Oxygen Concentration.

(e):

LaSalle County Station Technical Specification 3.10.5, Special Test Execption Oxygen Concen tra tio n.

Dea r Mr. Schwencer :

The NRC has recently issued References (a) and (b) which indicate inconsistencies between the Standard Technical Specifications *,

and specific audit requirements per 10 CFR.

The NRC has indicated that, notwithstanding the Technical Specifications issued by the NRC, the 10 CFR requirements must also be met because the Technical Specifications in these two cases were not meant as exceptions or exemptions.

Reference (c) states, in part, that " Effective May 4, 1982 o r 6 months af ter initial criticality, whichever is later, an inerted atmosphere shall be provided for each boiling light-water nuclear power reactor with a Mark I or Mark II type containment..."

8211230516 821118 PDR ADOCK 05000373 P

PDR

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s A. Schwencer November 18, 1982 i

Re ference (d) requires that drywell and suppression chamber atmosphere oxygen concentration shall be less than 4% by volume during the time period from within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a f ter exceeding 15% rated thermal power to within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing the thermal power to less than 15% rated thermal power.

i Re ference (e) grants a special test exception that Reference (d) requirements may be suspended during the performance of the b

startup test program until either the required 100% rated thermal power trip test has been completed or the reactor has operated for 120 Ef fective Full Power Days.

The purpose of this letter is to assure ; hat, in licensing l

LaSalle County Station, it was ano continues to 6e the NHC position that the LaSalle County Station Technical Specifications regarding j

inerting are governing and were issued as specific exceptions and exemptions to the requirements of Heference (c).

As you are aware, LaSalle County Station Unit 1 performed its initial critical on June 21, 1982.

Unless the NRC staf f notifies Commonwealth Edison to the con tra ry, it is Commonwealth Edison Company 's intention to perform inerting in accordance with license NPF-11 and the attendant Techriical Specifications.

If there are any questions in this matter, please contact this office.

Enclosed for your use are one (1) signed original and forty (40) copies of this letter.

Very truly yours, DW sulo sin C. W. Schroeder Nuclear Licensing Administrator i

1m cc:

NRC Resident Inspector - LSCS P.

P. Steptoe - IL&B 5454N

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