ML19312B862

Forwards Proposed Tech Specs 3.2,3.6,3.5.2.5,3.5,4.11,6.4, 6.5 & 6.6.2.2 Re High Pressure Injection & Chemical Addition Sys,Instrumentation Sys & Station Operating Procedures & Records

ML19312B862
Person / Time
Site:	Oconee
Issue date:	11/01/1976
From:	Parker W DUKE POWER CO.
To:	Rusche B Office of Nuclear Reactor Regulation
Shared Package
ML19312B863	List: ML19312B862 ML19312B869
References
NUDOCS 7911250063
Download: ML19312B862 (4)

Text

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'NRC DISTRIBUTION Pon PART 50 DOCKET MATERIAL DATE op ooCOMENT TO: Mr Rusche FROM: Duke Pwr Co 11~0-76 charlotte, NC W 0 Parker JR oATE RECEIVED pg

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Ler notartzed 11-1-76. . .trans the following: AMDT to OL/ Change to Tech Specs: Consisting of revisions with regard to miscelaneous topics with the intent to update & improve existing tech specs.............

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Duxs POWER COMPANY Powra Deit.nixo 422 SOUTH CHURCH SrazzT. CnARI.oTTE. N. C. 2e242 wn.u - o.un=ca.sa. November 1, 1976 v.c, p.c., o c,,, rea -o c a.c. 7:4 S f t a a. Pecooc, o 3 'l .gj 373 4083 Mr. Benard C. Rusche, Director g I g Nuclear Reactor Regulation gl N 8 gO ,,, pp h, U. S. Nuclear Regulatory Commission '

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Re: Oconee Nuclear Station A

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Docket Nos. 50-269, -270, -287 (7 g ' 6{ 4 T oA f A h

Dear Sir:

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/ }w ;g' Pursuant to 10CFR50, 550.90, an amendment to the Oconee Nuclear 'rinn.

Technical Specifications, Appendix A to Facility Operating Licenses DPR s

-27, and -55 is requested. These proposed changes concern several miscel-laneous topics and are intended to update and improve the Oconee Technical Specifications. Replacement pages for these proposed changes are attached.

The proposed changes to the Technical Specifications and the justifications are as follows:

1. Specification 3.2.2 requires availability of redundant sources of concentrated soluble boric acid, requiring in particular that at least one of two sources in addition to the borated water storage tank be available and operable. This specification has been changed to allow a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period to restore operability of at least one of these two sources should they become unavailabic; or a one hour period in which to restore the borated water storage tank to operability in the event it becomes unavailable. This change will provide more operating flexi--

bility by allowing for a reasonable period in which to implement correc-tive actions should one or more sources of soluble boric acid become unavailable. Specification 3.3.6 has accordingly been changed as indicated on the attached replacement page to provide compatibility between Specifi-cation 3.2 and 3.3 in the event that requirements of Specification 3.3.1(f) are not met.

2. A proposed change to Technical Specification 3.5.2.5.b allows a two hour period for restoration of control rod group overlap in the event the pre-scribed limit of 25% + 5% between two sequential groups is exceeded.

Provided that the required shutdown margin limits are maintained, this is considered a reasonably conservative time period in which to initiate appropriate corrective action.

3. Spec t f leat ion 3. 5.2. 5.d (2) has been reworded to requ ire that the xenon reactivity pass its final maximum or minimum peak prior to increasing reactor power above the power level cutoff, rather than stating, that 1130J

' Mr.'Benard C. Ruscha Paga 2 the xenon reactivity shall be asymptotically approaching the value for operation at the power level cutoff. This change is not a change in operational procedures but rather, provides for a clearer understanding of the intent of this specification.

4. Specification 3.5.1.4 currently prohibits the use of the key-operated shutdown bypass switch during power operation. Operation of this switch is required during power operation in conjunction with the channel bypass switch to perform complete calibrations of the Reactor Protective System. Operation of this switch with the channel bypass switch has no significance since the channel trip relay is locked in the untripped state. The use of a key-operated shutdown bypass switch alone would result in a channel trip.

5. Specifications 6.6.2.2 e and d require the submission of a written report whenever a measured level of radioactivity in any environmental medium exceeds the control station value by a factor of ten or four respectively.

Numerous reports concerning this subject have been submitted during the past year. Since the Oconee low level radioactive waste discharge is diluted only by the relatively low volume created by the Keowee dam leakage and the resulting radioactive concentrations downstream have been in accordance with levels predicted in the Oconee Final Environmental Statement, it is considered that these reports serve no useful function.

It is requested that the reporting requirements be revised to require this report when measured and control samples exceed a factor of 50 in order to -

provide a meaningful report.

6. Technical Specifications 3.5.2.7, Table 4.11-1, 6.4.1, 6.5.2 and Figure 6.1-1 have been revised as indicated to reflect recent administrative changes and are self explanatory.

Ve / truly yours, A. 40. e & -

William O. Parker, .

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Mr. Benard C. Ruscha

. Pega 3 -

Novemb:r 1, 1976 WILLIAM 0. PARKER, JR., being duly sworn, states that he is Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this request for amendment of the Oconee Nuclear Station Technical Specifications, Appendix A to Facility Operating Licenses DPR-38, -47 and DPR-55; and that all state-ments and matters set forth therein are true and correct to the best of his knowl ge.

1 Y u.e f.D.a.v - '

William O. Parker, Jr. W ce President ATTEST:

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//ohnC. Goodman,Jr. ~/

M ssistant Secretary (Seal)

Subscribed and sworn to before me this 1st day of November, 1976.

GL /Y u))Riv Notary Pu6lic (Notarial Seal)

My,Coc: mission Expires:

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