ML20125D582

Informs of Change 9 to License DPR-11,allowing Increase in Ramp Reactivity Addition Rates Under Certain Operating Conditions,Changing Shutdown Margin Verification Procedures & Permitting Other Minor Mods to Reactor Facility

ML20125D582
Person / Time
Site:	05000130
Issue date:	05/11/1966
From:	Doan R US ATOMIC ENERGY COMMISSION (AEC)
To:	Mcelroy D NORTHERN STATES POWER CO.
Shared Package
ML20125A538	List: ML20125D123 ML20125D151 ML20125D175 ML20125D208 ML20125D224 ML20125D241 ML20125D271 ML20125D310 ML20125D324 ML20125D333 ML20125D352 ML20125D364 ML20125D385 ML20125D404 ML20125D418 ML20125D526 ML20125D534 ML20125D541 ML20125D545 ML20125D551 ML20125D554 ML20125D559 ML20125D561 ML20125D563 ML20125D567 ML20125D571 ML20125D582 ML20125D587 ML20125D595 ML20125D618 ML20125D671 ML20125D691 ML20125D706 ML20125D718 ML20125D736 ML20125D760 ML20125D771 ML20125D787 ML20125D800
References
FOIA-85-54 NUDOCS 8506120410
Download: ML20125D582 (4)

Text

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. " * , gg I UNITED STATES plLE COPY T

ATOMIC ENERGY COMMISSIOkCENSE b -

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( WASHINoTON, D.C. 30848 o '

Al Docket No. 50-130 Y

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Northern States Power Company \j / ' r

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414 Nicollet Avenue l Minnesota, Minneapolis 55401 [

Attention: Mr. David F. McElroy

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Change No. 9 d

Vice President, Engineering Gentleasas By application dated April 4, 1966, the Northern States Power Company (NSF) requested authorisation of a number of changes to the Technical Specifications of License No. DPR-11 pursuant to the provisions of Section 50.59 of the commission's regulations. This request would allow (1) increases in ramp reactivity addition rates under certain operating conditions, (2) a change in the shutdown margia verification

( procedures, and (3) other minor modifications to the Fathfinder reactor facility. We have designated this request Proposed Change No. 9. These changes were requested as a result of operational experience and evalua-tion of Phase I and 11 test data.

Based on our review, we have concluded that Proposed Change No. 9 does not present significant hasards considerations not described or implicit in the hasards susunsry report and that there is reasonable assurance that the health and safety of the public will not be endangered. Our related safety evaluation is attached.

Accordingly, the Technical Specifications (Appendix A) are hereby .

changed as indicated in Attachment A.

4 Sincerely yours,

! Original Signed By l,

R.LDean

R. L. Doan, Director

! Division of Reactor Licensing

Enclosures:

1. AEC Safety Evaluation

2. Attachment A l

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! PAY 85-54 PDR ,

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- EY I 1 Igg ATTACHMENT A i

NORTHERN STATES POWER COMPANY CHANGES TO TECHNICAL SPEC {FICATIONS CHANGE NO. 9 - LICENSE NO. DFR-11

1. Section 4.2.1.2

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Delete the last sentences from the first and third paragraphs which read:

"(This shall correspond to a maximum reactivity addition rate of less than 5 cents /sec) ." and

" Reactivity addition by recirculation flow control shall not be continued for more than 10 seconds in any one 20 second interval."

2 section 5.6.1(b)

Change the maximum steam temperature in the table from "750'F" to "775'F."

3. Section 5.8.2 Delete the first sentence of the second paragraph and substitute the followings

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"The core shutdown margin shall be verified by a demonstration that the reactor is subcritical with the superheater in its most reactive condition, the most valuable reactivity-worth rod fully withdrawn, and other rods partially withdrawn. Immediately, subsequent to the withdrawal of the most valuable reactivity-worth rod, it shall be demonstrated that the rods partially withdrawn contribute 0.003 k gg or more to the effective aniciplication."

4 Section 5.3.2 <

Add the following to the last sentence of the second paragraph:

". . . and with the range switch of channels 5 and 6 set a positions  !

such that scram level shall not exceed 600 Ew for the duration of l the demonstration."

5. Section 5.13 Cheese the second paragraph to read:

"The maximum reactivity insertion rate when the k gg of the core is greater than 0.997 shall be 12 cents /sec except during the core shutdown margin verification of section 5.8.2, when it shall be approximately 34 cents /sec."

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5. saetian 6.1.1 Delete the words "and operation of the eastgency condenser." from the second paragraph. ,

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7. Section 6.1.7 Change the wording in the first table to resd:

" Condition Setooint (1) 14ss of all three Breaker Operation (msy be bypassed recirculation pumps through use of a key switch during rod latching and unistching and during verification of core shutdown margin)" i

8. Seetion 6.1.9.6 ,

Replace Table 2, " Nuclear system Annunciator Points" with an updated Table 2 (attached) dated 3/1/66.

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3/1/66 s

TABLE 2 r

NUCLEAR SYSTEM ANSUNCIATOR POINTS Superheater outlet temperature - High Reactor feedwater temperature - Low Superheater outlet pressure - High Reactor ' pressure - High i Turbine 1021 overspeed - Tripped ' '

Turbine trip-stop valves - Tripped Reactor Control - Runback Reactor Control - Scram Nuclear instrumentation reactor period - Short Mbin steam isolation valve by-pass flow - Low khin steam isolation valve - Tripped - Closed Nhin steam isolation valve - Loss of Power Superheater outlet temperature - Low

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Superheater outlet pressure - Low Main steam safety valves - Open

- Reactor recirculating pump motors bearing temperature - High Reactor recirculating pump motors - Overload Reactor recirculating pump motor temperatures - High Reactor recirculating discharge valves - Loss of Power 7' Reactor water level - High Reactor water level - Low Reactor feedwater temperature - High

. Reactor recirculating water temperature - Low Reactor feedwater temperature' control set point - Low Reactor building shield pool seals - Leaking Reactor building air lock doors - Open Reactor building pressure - High Reactor vent temperature - High Radiation - High, Isolation - Trip Reactor control rod drive motors - Overload Reactor' control rod drive motors - Loss of Power Reactor control rod drive motors ; Reverse Phase Reactor control rod drive seals leakage flow - High Main steam isolation valve interlock switch - Out-of-Position Nuclear instrumentation power range flux channels 7 & 8 - High Differential Nuclear instrumentation - Trouble Reactor pressure control pressure error - High - Low

- Nuclear instrumentation short period - Runback Trip Nuclear instrumentation channels, 5, 6, 7, & 8 - 2 of 4 Runback trip Reactor control loss of feedwater - Runback Trip Reactor control ejector exhaust high activity - Isolate - Scram Reactor control main steam dump valva - Low oil pressure Nuclear instrumentation channels 5, 6, 7, & 8 - Scram logic trip l

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