ML20069E759

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Proposed Tech Spec Changes Re Secondary Cooling Sys
ML20069E759
Person / Time
Site: 05000124
Issue date: 11/03/1982
From:
VIRGINIA POLYTECHNIC INSTITUTE & STATE UNIV., BLACKSB
To:
Shared Package
ML20069E719 List:
References
NUDOCS 8303220182
Download: ML20069E759 (13)
v • d • e


Text

_

PROPOSED TECHNICAL SPECIFICATIONS CHANGES O Page 3 Delete all of para. 5 add:

5.0 Secondary Cooling System 5.1 The secondary coolant system shall consist of piping, a cooling tower, pump, cold side of heat exchanger and a flow throttle valve.

5.2 The secondary cooling system shall be maintained at a higher pressure than the primary coolant system during reactor operation.

i 5.3 Secondary coolant water shall utilize corrosion and organic

, growth inhibitors.

Page 2 para. 4 change 4.1 to read:

4.1 The primary coolant system shall consist of piping, a storage tank, pump, hot side of heat exchanger, 2 core tanXs and a dump valve, demineralized water shall be used as the primary O coolant.

delete 4.3 change to read:

4.3 The components of the primary coolant system with the exception of the core tanks, heat exchanger and associated connecting pipes, shall be located in a process pit in the reactor room.

a. The process pit shall be large enough to contain the entire volume of primary coolant.
b. A drain into the process pit from beneath the core tanks shall be provided.
c. A sump pump which is normally shut off shall be the only means for draining the process pit.
d. A system of leakage control shall be employed to direct any potential leakage of primary coolant from the piping run.to the heat exchanger to the process pit.
O 8303220182 830315 PDR ADOCK 05000124 P PDR

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M AL5 A-1.AVAL January 3, 1983 Virginia Polytechnic Institute and State University Blacksbitrg, Virginia 24061

Cu GHK EE:S'E

Reference:

Our AP-9971, 30100-60507 Your Order #A28737 Gentlemen:

For your files, we are enclosing duplicate copies of Form U-l

" Manufacturers' Data Report for Unfired Pressure Vessels,"

covering the Heat Exchanger (s) recently shipped on your Order Number referred to above.

ud Form U-l certifies that the units were built in accordance with ASM.E Code Rules for the Construction of Unfired Pressure vessels and inspected by a certified inspecter.

?do ecpies of the data reports were forwarded to the National Board of Boiler and Pressure Vessel Inspectors in Columbus, Chio, with instructions for them to approve One copy and forward same to:

Department of Labor & Industry Boiler and Pressure Vessel Safety Division Chief Inspector, Vernon E. Doss Fourth and Grace Building, P. O. Box 12064 Richmond, Virginia 23241 Sincerely, d _, ')

{ .A)] i. , / a .4 e f: %

(y, Quality Control Manager fw Enc.

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CERTIFICATE OF COMPLI ANCE wwt struv that the statements in tNs resort are correct eae that eli cetsies of aes gm. matenas, constewetion, enc worm menom o of tms vesses comorm tc ran asuE Cooe toe Pressw ee vesseis, section v m. D..ision 1.

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/ CERTIFICATE OF COMPLIANCE FOR FIELO WORK W3 cSeidy emot the statements rance in tNs report see correct eno thet oil celeits of ces'Ga. mateei. constrwetion. eac wora mensme et tms vene. cor.

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. FORM U.1 MANUFACTURERS' D ATA REPORT FOR PRESSURE VESSELS As Recuired by the Provisions of the ASME Code Rul;s. S:ction Vill, Division 1

( ,) i. uan ut.civ.e. ,, Alf a-Laval, Inc. ~her:nal Supply

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, . .ae . .n Unit , Foughkeepsie, N. Y.

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2. v a wieciu.eo to, Virginia Polytechnic Institute and State University, Blacksburg, Va. 24061 __

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. 1 December 17 0 1982 SAFETY ANALYSIS RE: License No. R-62, Docket No. 50-124

SUBJECT:

Proposed Change to Technical Specifications TYPE: Administrative EFFECTS: We propose to change the current wording used in the Technical Specifications sections 8.1, 8.2, 8.3, 8.4, 9.2.1 and Table I - Safety System Functions to read " Reactor Safety Committee" instead of

" Radiation Safety Committee" wherever the latter appears. In 1979 the Radiation Safety Committee formed two separate subcommittes to more effectively perform their respective functions. One, the Radioisotope subcommittee was chiefly responsible for controlling, administering,

~

etc. usage of radioisotopes on campus. The other subcommittee, (Reactor Safety) oversaw and effectively performed the functions as outlined in Technical Specifi.ations. A joint meeting of the two subcommittee's was held annually termed-Radiation Sa'fety Committee.

Technical Specifications were not changed at the time to reflect this.

SUMMARY

Since the Reactor Safety subcommittee has been effectively per-forming all the listed functions administratively in the Technical.

Specifications this change will more accurately attribute accountability to the committee and eliminate the confusion with regards to separate subcommittees.

No other requirements for the overseeing of the reactor will change hence no safety questions exist.

Please note that no changes are necessary in our proposed Technical Specifications (for licenso renewal) as the Reactor Safety Committee is already used throughout the document.

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