ML20214S827

Proposed Tech Specs Pages 3/4 5-5,increasing Min Requirement for Trisodium Phosphate Dodecahydrate in Item 4.5.2.c.3

ML20214S827
Person / Time
Site:	Millstone
Issue date:	12/31/1977
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20214S825	List: ML20214S823 ML20214S827
References
TAC-7317, TAC-7420, TAC-7546, TAC-8169, TAC-8631, NUDOCS 8706090461
Download: ML20214S827 (3)

Text

..

DOCKET NO. 50 336 1

ATTACHMENT 1 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 PROPOSED REVISIONS TO TECHNICAL SPECIFICATIONS j B706090461 771216 DECEMBER, 1977 PDR ADOCK 05000336 p PDR

l February.2, 1976 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i l

8. Verifying that the following valves are in the indicated I position with, power to the valve operator removed:

Valve Number Valve Function Valve Position 2-SI-306 Shutdown Cooling Open Flow Control 2-SI-659 SRAS Recirc. Open*

2-SI-660 SRAS Recirc' . Open*

2-CH-434 Thermal Bypass Closed ** l 7-

b. By a visual inspection which verifies that no loose debris-  !

(rags, trash, clothing, etc.) is present in the containment '

which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:

1. For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and

2. Of the areas affected within containment at the completion of containment entry when CONTAINMENT INTEGRITY is established.

c. At least once per 18 months by:

1. Verifying automatic isolation of the shutdown cooling system from the Reactor Coolant System when the Reactor Coolant System' pressure is above 300 psia.

2. A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.

3. Verifying that a minimum total of 110 cubic feet of. solid granulartrisodiumphosphatedodecahydrate(TSP)is contained within the TSP storage baskets.

4. Verifying that when a representative sample of 0.35.*0.05-l21 lbs of TSP from a TSP storage basket is submerged, without agitation, in 50 1 5 gallons of 180 1 10'F borated water from the RWST, the pH of the mixed solution is raised to > 6 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• To be closed prior to recircu' ation fall wi[gclosed

• • 2-CH-434,amanualvalve,s1allbelocSe LOCA. *7 1

MILLSTONE - UNIT 2 3/4 5-5 X

DISTRIBUTION AFIR iMa#MW le/T#xA%gM1Qict415 U.S. NuCLsAA EstubAToRv coMMIEslEN '

NRC FCCM'196 is m g ooCKsT 3D - S NUM$b

" """**" l NRC DISTRIBUTION ron PART 50 DOCKET MATERIAL -

FROM: oars ce ooCuusNT To: -

Northeast Nuclear Energy Company 12/15/77 Mr. G. Lear Hartford, Conn. '

oats nacsivso D. C. Switzer 12/20/77 Moronizso Pace NeurponM Nuusen ce cortas asesivso M yrsn 2$.1tGINAL ,,McNCI.AEDelso Cicoev j $t(,6

.asesimoM ,

sNCLoSuns License No. DPR-65 Appl for Amend: $

tech specs proposed change to increase the volume of trisodium phosphate dodecahyd rate to ensure adequate pH control of the containment sump water during a LOCA.......

notorized 12/15/77.....

(2-P) (1-P)+( 2@))

, PLANT NAME: Millstone Unit No. 2 *

RJL 12/20/77 l l

SAFETT FOR ACTION /INFORMATION i IBRANCH CHIEF: (7) 1.E42

' 1 1 I I ,-

INTERNAt. DISTRISUTION I tREG FTT.y kice w n IT cem i inrr n I

L7AMATTTM l l i

ever r YTC - wi! r

- l I

t MUAO i fRA7W 97"f7 PR Wu Wrs LT . COT T TNE

' (

i LT. MCCOUCH l

. i ,

I I I I I (

' I 1 i l I

! l I i (

i i i i 8XTERNAL CISTRIBUTION

. CONTRCL NUMBER L?DR: nM7ftroth CW i i I!C l {

i t i NSIC 773540074 I

I acas 16 CTS SENT CATEGDRY N s l I c

a .. . 2, -. t a__ _ . _