ML20063K646

Application to Amend License DPR-35,clarifying Existing Tech Spec Re Number of Inoperable Control Rods During Power Operation

ML20063K646
Person / Time
Site:	Pilgrim
Issue date:	08/30/1982
From:	Howard J BOSTON EDISON CO.
To:	Vassallo D Office of Nuclear Reactor Regulation
Shared Package
ML20063K648	List: ML20063K646 ML20063K654
References
82-232, NUDOCS 8209080319
Download: ML20063K646 (3)

Text

. . _ . _ _ - . _ - - - .

d e'

BOBTON EDIBON COMPANY B00 BOYLETON STREET BoBTON MAESACHUBETTE O2199 J. EDWARD HOWARD visa enseio..?

-o.6...e........

August 30, 1982 4

3 BECo. Ltr. #82-232 Proposed Change No. 82-10 Mr. Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Operating Reactors l Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555 i

License No. DPR-35 a Docket No. 50-293 Proposed Change to Technical Specifications i

Dear Sir:

! Introduction Pursuant to Section 50.90 of the Commission's Rules and Regulations, Boston Edison Company hereby proposes the following modification to Appendix A of Operating License No. DPR-35 as shown on Attachment A.

l

! Should you have any comments or questions concerning this submittal, please contact us.

1 Very truly ycurs,

$v 3 signed originals and 37 copies  %(

Commonwealth of Massachusetts)

County of Suffolk ) 0 1 Then personally appeared before me J. Edward Howard, who, being duly sworn, did state that-he is Vice President - Nuclear Engineering of Boston Edison Company, 4 the applicant herein, and that he is duly authorized to execute and file the sub-mittal contained herein in the name and on behalf of Boston Edison Company and that the statements in said submittal are true to the best of his knowledge and belief.

,?

My Commission expires

C A, &"

Notary Public 8209080319 820830 i

PDR ADOCK 05000293 wnUAM s. :TDWE. fl0T4RY ruauc P PDR CDMMISSION &KPIRIS Jutg 30, m3

s .-

r Proposed Technical Specification Change Proposed Change Reference is made to Pilgrim Nuclear Power Station, Unit #1, Technical Specifications, Section 3.3 " Reactivity Control";

Add New:

Sections 3.3.G " Scram Discharge Volume" Limiting Condition for Operation and Section 4.3.G " Scram Discharge Volume" Surveillance Requirements as shown on Page 85 attached.

Add to Table 3.2.C " Instrumentation that Initiates Rod Blocks" instrument

" Scram Discharge Volume Water Level - High", Minimum # of Operable Instrument Channels Per Trip System and Trip Level Setting as indicated on Page 54 attached.

Add to Notes of Table 3.2.C Note #9 as follows "9. If the number of operable channels is less than required by the minimum number of operable instru-ment channels per trip system requirement, place the inoperable channel

! in the tripped condition within one hour," as shown on Page 55 attached.

Add to Table 4.2.C " Minimum Test and Calibration Frequency for Control Rod Blocks Actuation" instrument "(2.) Scram Discharge Volume Water Level - High",

instrument functional test requirements and calibration frequency as shown on Page 63 attached.

Change Pages i " Table of Contents" and Pages 84, 85 and 86 as shown attached.

Reason for Change i

This change is proposed in response to a USNRC request.- This request was made

in the NRC letter of July 7,1980 from Mr. Darrel G. Eisenhut to All Operating Boiling Water Reactors. This request was reiterated in a telephone conversation between the NRC (Division of Licensing) and BECo Licensing and PNPS personnel on August 27, 1981.

! Clarification

\

This proposed change will clarify an existing Technical Specification, Section 3.3. A.2.e that states "During reactor power operation, the number of inoperable control rods shall not exceed eight. Specification 3.3.A.1 must be met at all

! times ." The addition of the vent & drain valve surveillance will assure proper operation to verify the scram discharge volume header operational. The vent and drain valves surveillance requirements were developed frvm the Technical Specifi-cations approved for Browns Ferry, Unite I, II & III and its associated Technical Evaluation Report to the NRC as prepared by Franklin Research Center. This Tech-nical Specification Change was approved for Browns Ferry, Units I, II & III in Amendment Nos. 83, 80 and 54 respectively.

Safety Considerations This change does not present an unreviewed safety question. It has been reviewed and approved by the Operations Review Committee and reviewed by the Nuclear Safety Review and Audit Committee.

Schedule of Change This change will be put into effect upon receipt of approval by the Commission.

Fee Determination Pursuant to 10 CFR 170.12, Boston Edison Company proposes this change as a Class III.

4 r

e