ML19253A533

From kanterella
Jump to navigation Jump to search
Submits TMI Daily Rept Re Reactor & Plant Status,Radwaste & Health Physics & Environ Measurements
ML19253A533
Person / Time
Site: Crane Constellation icon.png
Issue date: 05/25/1979
From: Vollmer R
Office of Nuclear Reactor Regulation
To: Stello V
Office of Nuclear Reactor Regulation
References
NUDOCS 7909100227
Download: ML19253A533 (5)
v • d • e


Text

. 8# fog %

UNITED STATES 0

,.4 NUCLEAR REGULATORY COMMISSION j-33!g@w ') /, j WASHINGTON, D. C. 20s55 n

o %.. 7./, g

? yps[

.M, May 25,1973 MEMORANDUM FOR:

Victor Stello t

FROM:

R.

Vollrer e

S 'JB J ECT:

TMI DAILY REPORT A.

Raactor and Plant Status 1.

See Attachment for Technical Working Secup agenda and notes and for plant status surrarv.

2.

Recheck of t"e R3 sump level af ter instrurentation calibration check shcwed an adci t iona! increase o# about 6" above yesterday's reading, or about 12" above t'at of a week aco (7.2' above the #1 oo r, 21 eva t i co 233.6').

Th i s pu t s the botton of the l i c'i t s.s i t ch cova c' 7 '/?

under water. / bubble was draan, RCS pressure r2duced to 300 ps: f,25, and JH-V2 was Openad. Arcther leve!

check wil! be ace later today.

3 A seal cavity PI has been lost since vesterday, in add;* ion to thase previously reported.

Investigatic7, test,and corrective at: ions we e iscuss2d

+

and are underway relative to 2. and 3. ac;ve, as !denti#:ed in tne atta:nec 'A c t i nn iters cate: 5/:/73 Thes2 cea' sith additional p essure and level inaication, cans, so.,rce of leaks, oossible move ent o# water out of acntainment, and possible containrent purge.

'hese and other actions were discussed at a brie # Tecnn i cal 'in -k i ng G roup cet i-g at 1: 30 today.

5.

'3 CT3G system :s in ecir:Jiatien.

3.

0 9 t-ta s t e and HP A'i charcoal cdsorcers have caen chancec 0; i-

?

building "3'

-ain, in the course o' crange out ' 'I?A ci!!ers were da aged and 2placad.

In addition t'. < c te peratu re sensor s we re becen anu s;asa quen ti-

-',;a s s 2.

and t"e # ire de ' uge s.'s te-en e r gi c2J up :: t'2 ic'!ati n salve.

A sc p's cart ~;ga O'

~' 2 7.;., ' j ' n -

- ai-a i-

,Cs r e O,- 2 0 anu t;'I 20 29t t'. 4 0 $ C.'.

'I m;Js, 7^

C

")

l 7909100-27 7

~

Vi-tor Itallo 2.

tee ven t i la t i an systems for *be 210:09-11 process was ratested and passed tha # con test-3.

Tha two l ow ? r tanks i n the tank #ar were #illed wi

E.

water and #!ucracine dve and leak tested.

The aa te r siii then be pu, ped to the c our upnar ta,ks using

  • 'e stca-ed.c* ors and leak tested.

Jsing the sacand ed tor '52 water a i l ' ee pu~ ped t o te two tanks in !be IPl:0R-l:

building and leak testad.

The leak testing O'

c

  • cnk
  1. ar an: per#cr.mance testing
  1. *"e eJuc*crs s' alH. '

r

_ v_ o 1.,.

m. s..u

,o

,a c o q,., a.

p -._.,,,

v-

,.. a !.n_-,.,_

,e

-t...

7 y.

-," ' - a' }. l l -. p g.J:m. e cLs. l.-

k. n.

.' /

p '. -- - e Jr g*,1

- i

==m-a 2,

~,

y., ' e. ; -, n., * -T s_e _e

. m r. e,

  • " f

..i 1*.-'

  • ,'-'h 1*

r,

-,g r y a.. f c.

. - 3 a3., _,

6 35*/

,)

c '/ t' 3

3'P 8" O

u l

f^h

  • ).

)

r._.s,.,,,...,,.,Q.

- ~-

,3

.-,.a.

.a.

.... -. ~

v u

?,..,Jc f.'

J..'-)

,=

-of-s.-. -.,,

3 a

g

,,?.3Jo. 4 e

[ 9 ' s f*

f}

  • g s

q%2 3

a,a,

< 3 e

i 6

?',

f,..,

J

    • . 3

'.. e g ] s,,. 4 s u. '.

c.

e, 4

,J f..:-

-.-.i.-

  • L-a

,e

  • na4 ?, n.

. '. p n C

2-

~

'c..',**

3pr<= pee' a-.-4m.

\\w m

  • w

.. m u e

..f U e

-4 n_.,.3.

7

. a,m.-^m um

?.,3.3]c u.

e re-n L

u

  • f'

e 1

}.

.^AT

' -[ y } 's.-a,.maa -6, y 3 3 ., 3., a. a . s a

  • ,,3. %,, r c,,,.

7,, .L, .6

  • L, ! c 4

4' l p 4.3.3.-.-- .','t g h -u?L / t 1 w ..,n..--n.-. I 3, g]. L I, .C. --., a "%Y f Y -e

  • J g

W. g .,.i e W .... ". $ Q 4 ,(, p a

  • d s

s e : --,- p6 3 yA -e E e e

5/25/79 AGENDA TECHNICAL WORKING GROUP 0900 5/25/79 1. Radioactive Releases a. 748, 219, Anvil L2ry Buil. ding Fans ] b. Point Sources ${tD'D-2/- e '5 ' 5 e - 3 c. Dome Monitor - Contain=ent urvey v w, f 4 ,J,_ l . c s-g W R a3.b ,+ l

  • d-2.

Plant Status a. a. RCS Profile b. Plant Operations Schedule Pressurizer Bubble Operation Reactor Building Sump Level Measurement 6 Of J..L. n a,-e.-.a g &c l.l. 3 P.I p d-Replacement of "B" Train FH3 Charcoal Filters upL,f o 4 -v5. 3. Analvsis a. Reevaluation of existing recommendation to draw a bubble vs. solid operation. b. Reduction to 300 psig - Increase in loss of pressure protec-tion? c. Reevaluate the curve supplied for throttling steam bypass based upon pr(1ent temperature and pressure conditions. 4. Construction Status Estimated Comolecion a. RCS Pressure /Yolume Control Turnover f,{.,. for Testing 6/1 s-b. Alternate Decay Heat Re= oval System Tie-ins 6/16 5. Preoperational Testing 3'< b } [-C IY u ~ 7 fh' { '".!f " " ' a. Tank Farm (Zero Leak Testing) QL ex ~ b. OTSG "B" Long-Term Cooling I ti im^ c. EPICOR (CAP-GUN II) he g [- bl / / < % o,. e le T, e+ P00RORRNM u =

5/25/79 RELEASES 0500 (5/23/79) 0500 (5/24/79) 0500 (5/25/79) -9 -9 748 6.20 x 10 6.17 x 10 out of service -1 -9 219 8.10 x 10 5.23 x 10 out of service -9 -9 5.30 x 10 ' O.23 x 10 3.22 x 10 Inlet -1 -1 -12 Train #1* 7.00 x 10 5.06 x 10 5.73 x 10 -1 -1 -12 Train #2* 7.40 x 10 6.63 x 10 7.43 x 10 Train #3* 6.72 x 10 4.24 x 19 1.72 x 10-2 -12 -1 Train #4* 6.37 x 10 4.41 x 10 5.08 x 10- -12 -1 REACTOR COOLANT SYSTEM PROFILE PLANT STATUS 0500 (5/23/79) 0500 (5/24/79) 0500 (5/25/79) A B A B A B Th 167.5 168.6 167.1 168.2 165.8 168.2 Tc 155.6 100.7 156.1 98.7 154.7 97.4 6T 11.9 67.9 11.0 69.5 11.1 70.8 Tsts 153.9 125.0 153.3 125.5 152.4 125.5 7 ,SjiEnf' 37 7$ PZR Level Cal. Solid Solid DVM Lt-3 229.5 R.C. Press. Heise - 425 Heise - 420.0 Heise - 310.0 DVM - 427 DVM - 423.3 DVM - 300.0 S/G Level 430" 96 410" 96: 428" 96% Turb. B/P 50% Closed 56% Closed 56% Closed I.C.T. High 301.7 300.8 299.6 Avg. 191.6 -.~ 189.9 M.U. Temp. 129 125 127 i s' /

5/25/79 ACTION ITEMS TECHNICAL WORKING GROUP 0900 5/25/79 Item Action 1. Install pressure indication between DHV-3 and the building wall. Herbein 2. Verify contain=ent level reading and evaluate the possible air Herbein/ gap in sensing line. Wilson 3. Evaluate magger readings oc DHV-2 to obtain additional information Herbein/ concerning actual containment building level. Wilson 4. Evaluate operationally testing the reactor building coolers for Herbein possible leakage 5. Modify procedure such that a complete lineup for containment Wilson / level check is acco=plished with the exception of DHV-6B and Herbein provide minimum daily level checks. Provide reading early on second shift 5/25/79. 6. Continue pressurizer bubble mode cperation under present plant Herbein status until 1:30 - 5/25/79. 7. Evaluate evaporative cooling system surge tank as a means of Herbein providing additional information concerning R.B. leakage. 8. Evaluate electrical outlets / components as a possible source Wilson / of level indication and deter =ine the ne t critical electrical Cobean components above DHV-1 and 171. IN h w.C2 9. Evaluate the options of water movement from containment and Rusche pressure relief in the form of vent or purge operation of the containment for 1330 5/25 meeting. 10. Evaluate the availability of the tank farm and the possible Wilson / sources of leakage to the building containment for 1330 5/25 Herbein meeting. 11. Evaluate existing data concerning level determination for Cobean/ accuracy for 1330 5/25 =eeting. B&W/ Wilson 12. Provide holiday coverage for shield installation of Tank Hirst Farm Pump. jDb ( -}}

Retrieved from "https://kanterella.com/w/index.php?title=ML19253A533&oldid=4884970"