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g,. i OPT F99ht se0 te UNITED STATES GOLANMENT Memorandum DATt:
FEB 151962 To W. B. McCool, Secretary a-guh tion U10) H. L. Price, Direc l'R OM :
1.
wenstein, Director Division of Licensing and Regulation suejtcT:
ISSUANCE OF AUTHORIZATIONS TO SAITON NUCLFR EIPDLIMENTAL C m PORATIQi, DOCKET NO. 50 1h6 SDBOL:
DIARtRFB The Division of Licensing and Regulation has authorized Changes Nos.1, 2, and 3 in the Saxton Nuclear Experi2nental Corporationsia facility.
Change No.1 authorizes a change in the Technical Specifi-cations which permits a decrease in sensitivity in the startup source range instrumentation.
Change No. 2 authorizes a change in the Technical Specifi-catinns which permits a change in the mode of operation of the reactor's charging pumps.
Change No. 3 authorizes a change in the Teclnical Specil'i-cations which changes the definition of the unit of the limit for conductivity of the make up water to the reactor to correct a typographical error in the original Technical Specifications.
Copies of the Authorizations and related Hazards /nalyses are attached for the information of the Comissioners mant to Cornissioner 01 son's request following the bo's decision on chow cr-ce in the General t'
Mecitos Cace Cupi f *he Aut%ritations and Haznrds Analyvou le a bee
- Pablic Locument, Room, made a part of tne record cene ov vu.
in the case, and sent to the ACRS. The matters were dis-cussed with the ACRS and they indicated that they did not desire to review them formally.
Attachments:
1.
Authorizations for Changes Nos. 1, 2, and 3 (7ofeach) 2 Hazards Analyses (7 of each)
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e 9104190186 910314 PDR FOIA DEKOK91-17 PDR
i UNITED STATES ATOMIC ENERGY COMMISSION D l' l
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FEB 151962 Docket No. 50-lh6 Change No. 1 Saxton Nuclear Experimental Corporation P. O. Box 5h2 Reading, Pennsylvania Attention: Mr. D. R. Rees 4
General Manager Gentlemen This refers to your Change Request No. 1 dated January 11, 1962 requesting AEC authorization to make a change in the Technical Specifi-cations in License No. DPR-b pursuant to paragraph 3.B. of the license.
We have reviewed the proposed change in Section 7.(j) of the Technical Specifications and have found that authorizing a decrease in the sensitivity of the source range startup instrumentation in the manner proposed'does not present significant hazards considerations not-described -
or implicit in the Final Safeguards Report, as defined in License No.
DPR-h, and that there is reasonable assurance that the health and safety of the public will not be endangered by +oeration of the reactor under
- g the proposed Technical-Specifications change. A copy of our related j
hazards analysis is enclosed.
In view of the foregoing, Technical Specification 7.(j) is hereby amended in its entirety to read as follows:
- 7.( ' N w Wnstrumentation consiste v e
' range and-1~t&
- rl". range channel" a.
Wurae Mup }c gum *h cover 5 docades starting no higt."
t.har.- V 2 10 nv dle in+6 =cdinte range deutels cover -
er from 2.5 x 102 nv to 7 x 10 nv which is up to 10% of full power, provided; however, that if_ a minimum rate of 5 counts per second is not achieved during startup, the instntmentation shall.he 2.5x10ghangedsothatsourcerangechannelscoverfrom nv to 2.
3 nv whi cover:from2.5x10gx10nvto7x10geintermediaterangechannels nv.
There is a fast startup rate scram which is initiated by the intermediate range channels."
Sincerely yours, I
Original signed by R1.Khii Enclosures "4
Director Hazards Analysis Division of Licensing and Regulation
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l HAZARDS ARA IS BY THE RESEARCH AND POWER R ROR SAFETY BRANCH DIVISION OF LICENSING AND REGULATICN IN THE MATTER OF SAITON NUCLEAR EIPERIMENTAL CCRPmATIN DOCKET NO. 50-lh6 Introduction Pursuant to paragraph 3.B. of License No. DPR-h, Saxton Nuclear Experimental Corporation by Change Request No.1 dated January 11, 1962, requested authori-sation to change paragraph 7.(j) of the Technical Spocifications to authorize a decrease in the required sensitivity of the source range startup instrumenta-tion and to correspondingly change the Final Safeguards Report to include the decreased sensitivity.
Discussion The sensitivities and ranges of the startup source range instrumentation are as followst Sensitivity Range (See Table 203.3, Final Safeguards Report)
Original h0 counts /sec/nv 2.5 x 10-2 to 2.5 x 103 nv Proposed 13.3 counts /sec/nv 5 decades startgng no higher than 7.5 x 10- nv.
We have noted that the sensitivity of the startup channel detectors would be decreased by a factor of 3.
However, under the proposed revised Technical Specification,' if a mini = = rate of 5 counts per second is not achieved-during startup, the instrumentation vill be changed to cover the range oriEinally speM.% With the proposed sensitivity and range thn min 4=i=
detectable nt u t,- muld be 1 count per seco-d, We-k ileve that, t.he r uimu "nt pror.aca a.ndric W tij u ta achieve t'
auoquate measurement of neutron 4.c.luiplication during startup operatic and that tha proposed ehenge vill not. adveraely affect the safety of the Sarton facility.
Conclusion
- We have concluded. that the proposed change in the Technical Specifications requested by Change Request No.1 does not present significant hazards con-siderations not described or implicit in the Final Safeguanis Report, and that there is reasonable assurance that the health and safety of the public will not be endangered by operation of the reactor under the proposed Technical Specifications change.
Oriinal m.ed by ht(tt H. Bryn Robert H. Bryan, Chief Date:
FEB 1 51962 Research & Power Reactor Safety Dranch Division of Licensine end Reculat. inn flDIf/fjbfD l
1 UNITED STATES ATOMIC ENERGY COMMISSION l
I WASHlHGTON 15. D. C.
i RB 151962 Docket No. 50-lh6 Change No. 2 Saxton Nuclear Experimental Conoration P. O. Box 5h2 Reading, Pennsylvania Attentiont Mr. D. R. Rees General Manager Gentlement This refers to your Change Request No. 2 dated January 11,1%2 requesting AEC authorization to make a change in the Technical i
Specifications in License No. DPR-b pursuant to paragraph 3.B.
of the license, We have reviewed the proposed change in Section 12. of the i
Technical Specifications and have found that changing the mode of operation of the charging pumps in the manner proposed does not present significant hazards considerations not described or implicit in the Final Safeguards Report, as defined in License No. DPR-h, and that there is reasonable assurance that the health and safety of the public will not be endangered by operation of the reactor under the proposed Technical Specifi-cation change. A copy of our related hazards analysis is enclosed.
f In view M -
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+echnical Specification 10, 1
amend M u.y e d as followst i
"12.
A charging.rystam concistlag of two mul,or-driveu horizontal, triplex, reciprocating pumps, each having an adjustable capacity of 3 to 15 cpm at a total dynamic head of 2500 peig, is provided to charge degasified, domineralized make-up water, concentrated borated water, and water from the purification system back into the main coolant system. These pumps will be in operational condition during power operation of the reactor and will operate intermittently as required for the purification system and for volume control of f
the main coolant system."
I Sincerely yours, driginal SWd by R L. Kirk g'
Enclosurer M
Director J M C % M, u u M t ~ y p
HAZARDS ANALYSIS BY THE RESEARCH AND PCWER REACTOR SAFETY BRANCH DIVISION OF LICENSING AND RfDU1ATION IN THE MATTER OF SAXTON NUCLEAR EIPERIMENTAL CORIORATION DOCKET NO. 50-lh6 Introduction Pursuant to paragraph 3.B. of License No. DPR-b, Sarton Nuclear Experimental Corporation by Change Request No. 2 dated January 11, 1962, requested authorization to change paragraph 12. of the Technical Specifications to change the mode of operation of the i
charging pumps.
Discussion The present_ paragraph 12_of the Technical Specifications requires continuous-operation of the charging system regardless of whether the system is'in the normal operating condition or slut down.
Since during many phases of operation of the plant 'it may not be necessary to have this system in continuous operation, Saxton proposes to maintain the coolant charging pumps in operational con-dition during power operation of the reactor, and to operate them as required for the purification system and for volume control of the main coolant system.
We believe that this proposed change in the mode of operation of 3
the charging system vill mt adversely affect the safety of 'ir Saxton FacDR.
1 O?ncl?Slon We have -concluded that the proposed change in the Technical Specifications requested by Change Request No. 2 -does not present significant hazards considerations not described or implicit in the Final Safeguards Report, and that there is reasonable assurance that the health and safety of the public will not be b'
endangered by operation of the reactor under the proposed
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Technical Specifications change.
a Originahigned by Robert H. Bryu Robert H. Bryan, Chief Research & Power Reactor Safety Branch Division of Licensing and Regulation FFR 1
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r UNITED STATES t,
ATOMIC ENERGY COMMISSION
- l l* l WASHINGTON tl. D. C.
f!61 51962 Docket No. 50-lh6 Change No. 3 Saxton Nuclear Experimental Corporation P. O. Box 5h2 Reading, Pennsylvania 1
Attention: Mr. D. R. Rees General Manager Gentlement This refers to your Change Request No. 3 dated January 11, 1962 reauesting AEC authorization to make a change in the Technical Specifications in License No. DNb pursuant to paragraph 3.B of the license.
We have reviewed the proposed change and have found that changing the conductivity unit in paragraph h(a) "Make up to Reactor Plant" from " micro-mho" to " micro-mho per centimeter" does not present significant hazards considerations not described or implicit in the Final Safeguards Report, as defined in License No. DPR-h, and that there is reasonable assurance that the health and safety of the public will not be endangered by operation of the reactor under the proposed Technical Specifications change.
A copy of our related hazards analysis is enclosed.
In view of the foregoin"
- chnical Specification li(a) 3 T'y' Ma'r e n to Reactor Plant, [.tv u-
. j i' hereby amended to r">
follows:
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n M ty leen than O.$0 micsg-mho i nu e '
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Sincerely yours, Original signed tr/ R1 Kirk Deputy Director Division of Licensing and Regulation Enclosure Hazards Analysis Y) 0 4-()$TGO32.
HAZARDS ANALYSIS BY THE RESFARCH AND POER REACTOR SAFETY BRANCH DIVISION OF LICENSING AND REDULATION IN THE MATTER OF SAXTON NUCLEAR EXPERIMENTAL CORPORATION DOCKET NO. 50-lh6 Introduction Pursuant to paragraph 3.B. of License No. DPR-h, the Saxton Nuclear Deperimental Corporation by Change Request No. 3 dated January 11, 1962 requested authorization to change an item in paragraph k(a) of the Technical Specifications to correct a typographical error.
Discussion Saxton reouested that the unit of the limit for conductivity of the make up water to the reactor plant be changed from " micro-mho" to "nicro-mho per centimeter." This change involves no hazards consideration.
Conclusion We have concluded that the proposed change in the Technical Speci-fications requested by Change Request No. 3 does not present significant hazards considerations not described or implicit in the Final Safeguards Report, and that there is reasonable assurance that the health and safety of the public will not be endangered by operation of the reactor under the proposed Technical Speci.fications change.
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j i / I di + R#v33 Robert H. Bryan, Chief Research & Power Reactor Safety Branch Division of Licensing and Regulation FEB 1 51962 Date:
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