ML20085D188

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Change Rept 7 to Application for Amend to License DPR-4 Re Final Safeguards Rept
ML20085D188
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 03/14/1963
From: Neidig R
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 2032, NUDOCS 9110150328
Download: ML20085D188 (3)
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SAXTON NUCLEAR EXPERD1 ENTAL CORPORATION  :

DOCKET NO. 50-lh6 LICENSE DPR-h .

CHANGE REPORT #7

1. Applicant hereby submits Change Report #7 '.n compliance with paragraph 3(B)(1) of License DPR-h. This change pertains to item F on page 221.2 of the Final Safeguards Report. A revised page 221.2, dated March h, 1963, is attached to this change report.

SAXTON NUCLEAR EXPERIMENTAL CORPORATION By /s/ R. E. Neidig (S E A L) President i Attest:

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/s/ R. E. Sypher f/ .x l

Secretary

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Sworn and subscribed to before me. this lhth day of l March 1963

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/s/ George A.~Hiester

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Notary Public l- Muhlenberg Township, Berks County l - My Commission Expires August 31, 1963 9110150328 910424 PDR FOIA PDR DEKOK91-17 f

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March ih,1963 Docket No. 50-lh6 DPR-b Change Report #7

1. Description of Change A radiation shield consisting of a concrete base, solid concrete blocks, and lead bricks has been installed around the purification surge tank in the charging pump room. Item F on page 221.2 of the Saxton Final Safeguards Report has been revised to reflect this change. A revised page 221.2, dated March h,1963, is attached to this change report.
2. Purpose of Change This additional radiation shielding is required in order to reduce the radiation level both in the charging pump room and in the areas immediately adjacent to the charging pump room. The radistion in these areas results from the eccumulation of fission product gases in the top of the purification surge tank during power operation. Calculations show that the radiation level in the charging pump rocm should be reduced to a level less than the 100 mrem /hr, 1

the level designated in 10 CFR 20 as a high radiation level, and the level outside of the charging pump room will be such that it will not result in an i

accumulated dose in excess of that specified in 10 CFR 20 for restricted and unrestricted areas.

3 Conclusions l

It is our conclusion that this change does not involve a change in i

the Technical Specifications or any unreviewed safety question and that the health and safety of the public will not be endangered by this change.

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221.

Supplementary secondary shielding is provided external to the contaitunent vessel. The reactor ccanpartment is surrounded by a 3-foot thick concrete vall extending from 5 feet below grade to a point 3 feet above grade. The pipe tunnels outside the reactor and primary ceropartments are shielded by 3 feet and 2 feet concrete slabs respectively.

The operating floor over the primary compartment consists of a 3 5-foot thick concrete shield vhich serves to reduce the sky shine radiation frcan the primary equipnent to belov 2.0 mr/hr. In addition to providing safe radiationlevelsoflessthan2mr/hroutsidethecontainmentvesselduring i

full power operation, the secondary shield serves to reduce the shutdown radiation levels to permit extended access times within selected areas of the container.

The control rod rocan, in which are located the control rod drive mechanisms, is shielded by an iron-shot filled tank which vill reduce the radiationlevelsinthatareatolessthan15mr/hreighthoursafterthe plant is shut down. Penetrations in the secondary shield have been arranged to minimize streaming effects and where necessary supplemental shielding has been used.

E. Fuel Handling Shield The fuel handling shielding is designed to insure protection to personnel during the unloadin6 of 8 Pent fuel elements and control rode.

' The reactor shield ccenpartnent vill be flooded to a level of 17 fe'et above the vessel seal line during the refueling operation to provide shielding and cooling for the spent fuel assemblies.

F. Auxiliary Shield Auxiliary shielding is provided to protect personnel in the control and auxiliary building from the radiation emanating ircan the equipnent located

! in the charging pump area. The shielding consists of n 20-inch thick poured concrete interior vall and ceiling and a 12-inch thich poured concrete exterior l vall. The purification surge tank in one end of the charging pump rocan is shielded with a separate close fitting shield consisting of a poured concrete l

base, and a ecunbination of solid concrete blocks and lead bricks.

G. Design Basis l

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The design criteria for access to thic plant require that no one enter the containment vessel when the reactor is hot critical or operating l

at power, and that the plant site be evacuated in case of a major 2 tactor accident. The following radiation levels were used as design criteria for specifying shielding:

l Continuously occupied area 0.25 mr/hr l

Intermittently occupied working areas 0.75mr/hr i

Intennittently occupied ground level area during operation 2.0 mr P Fuel handling area during refueling operations 2.0 mr r l NDS allevable dose rate (based on 40 hr. Week) 2.5 mr r Na ud. March L.1963

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