IR 05000321/1986041
| ML20245B838 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/23/1986 |
| From: | Nejfelt G NRC |
| To: | Cantrell F NRC |
| Shared Package | |
| ML20245B770 | List: |
| References | |
| FOIA-87-76 NUDOCS 8707010340 | |
| Download: ML20245B838 (36) | |
Text
{{#Wiki_filter:I wo e m**CM p,AJT-M&t.ooI ' iy December 23, 1986 kg I
, MEMORANDUM FOR Floyd S.
Cantrell, Jr., Section Chief N Sj$ [ ' Reactor Projects Section #2B I 'p+/,- I " Division of Reactor Projects (DRP) . ' . (_ FROM: Gregory M. Nejfelt, Resident Inspector Plant Hatch - Section #2B, DRP SUBJECT: SUPPORTING MATERIALS FOR NRC AUGMENTED INSPECTION ' TEAM (AIT) REPORT 50-321,366/86-41 l The documents requested on December 23, 1986, are enclosed as' referenced.
The verbatim procedural compliance requirement is stated in 10AC-MGR-003-OS, Section 5.3.1.2, Enclosure (1).
Also, Enclosures (2.a) and (2.b) were the deficiency control procedures that were respectively in ef f ect during the event and af ter the event.
' The air regulatory, transfer canal seal, and other equipment that j are addressed in the AIT inspection report do,not have maintenance j part list (MPL) numbers, because no safety determination was made for this equipment..The licensee has requested its architect / ' engineer, Bechtel, to evaluate these components.
A preliminary summary of items that are being considered will be forwarded to thiis office by the licensee on December,30, 1986.
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- Gem M.
Nej t g,, Resident Inspector
Plant Hatch - l l ^ Enclosures * 1.
Preparation and Control of Procedures, ) 32T-j/2[3/ i C 10AC-MGR-003-OS, Revision 5 g ' -- 2.
Deficiency Control Procedure, [1*p b Y" a.
10AC-MGR-004-0 Revision 0 f.
h,M ' b.
10AC-MGR-004-OS, Revision 1 . 3.
Plant Operations, y @p , 30AC-OPS-003-OS, Revision 0 0 /sA'#b'k * 4.
Daily Inside Rounds, j p/ j
34GO-OPS-030-1S, Revision 3 5.
Daily Inside Rounds, % gj**dA dffdf w' 34GO-OPS-030-29, Revision 3 ..,r u 6.
Robertshaw Level Switch Calibration, f, / 57CP-CAL-094-2, Revision 1 7.
Hose Station Valves Standing Order, LR-OPS-002-0286, dtd 02-03-86 ',' 8.
Hose Station Valvec Standing Order, " LR-OPS-001-1285, dtd 12-05-85 9.
Long Term Recovery Program, LR-VPH-014-1286, dtd 12-08-86 10.
Special Task Forces, Committees, and Work-ing Groups, AG-MGR-05-0384, Revision 0 11.
Potential for Loss of Water from the q_' Refueling Cavity, IEN No. 84-93, [bjL '/h-f 7 - 76 dtd 12-17-84 8707010340 870619 D/bf ' n-PDR FOIA MURPHYB7-76 PDR ,
_ ... . _...._ - ___ - __ _ _ _ - _ _ _ _ _ _ _ _ _ - _. . DRAFT -- Enforcement Conf. Summary 1-27-87 -- Rev 0 . SUMMARY
l An enforcement conference was held on January.2 2, 1987, in the Region II offices with Georgia Power Company (GPC).
The subject of th'is conference was the potential enforcement actions stemming from the loss of fuel pool level by ] means of a leak by the fuel pool transfer canal seals.
! l The conference was opened by DR. Nelson Grace who asked if GPC understood the NRC concerns. When GPC responded'that they were ready to address the NRC
l concerns the floor was turned over to GPC for their presentation.
. I
} GPC reviewed the event and the actions taken to contain and clean up the l l contaminated water lost from the fuel pool, No information presented in this -) i area was different than what was previously understood to have occurred.
l i . ! The NRC had a concern as to whether the transfer canal seals were adequately ! f designed to prevent a significant loss of contaminated water from the fuel ' ! pool as specified by Criterion 61 and 64 of Ap p en d i >> A, General Design Criteria (GDC).
GPC stated that their analysis of the seal design indicated that it was proper and in accordance with GDC and NRC Safety Guide 12 which implements GDC 61.
GPC also stated that all FSAR commitments were met.
The air supply tc the seals was stated to be redundant but not single f ailure proof.
The redundancy was achieved since the Unit 1 and Unit 2 service air Fo 2 0 - F?- 7(, b/y3 ,
- -_ . . _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ l c' i i DRAFT - Enf orcement. Conf. Summary ' l-27-87 -- Rev 0 headers had manual cross connect capability on the 112' el eva t i on but not nn the 228' level of the refueling floor.
{ The FSAR states that interconnected drains behind the stainless steel fuel pool 1iner wi11 prevent uncontrol1ed Ioss of contamimated fuel pool water to I
other relativel y clean areas within secondary containment.
GPC stated that i this FSAR commitment only applied to the fuel pools not the transfer canal.
GPC made the point that the loss of water from the fuel pool was a spill not , I an unmonitored release since all the contaminated water remained on the plant . j site until properly processed through the radwaste system and properly discharged.
GPC agreed that there were personnel errors committed and that there were procedural problems contributing to the ovent and that corrective action in the' form of personnel discipline and procedure changes had been taken.
The questions of the adequacy of the seal and air supply design and of the applicability of the FSAR section on fuel pool liner leakage detection and water containment will be the subject o+ further NRC revi ew.
The NRC appreciated the quality and frankness of the GPC presentation.
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- J ' s ,? * . - \\ ' frtteroffice Correspondence Georgia Power h Date: GM-85-323 Re: Plant E.
I. Batch sota 85-1.* Reactor cavity Seal Failure" From:5. C. Wir To: J. T. Beckhan 1.
Summary of Boot docunest's subiect(s): During preparation ter refueling, the reacter mavity.eeal between . ' '. + @Abe deacter -vessel Slange and 1r.he refueli desvity floor failed.
I
- ^.q__
water -am the refueling sevity. era gepidir to tha . [.
- 1Amenta' lament floor. ' At h time.et the eventJf.$he reacter whe-
^! bead had been removed, tut ma arradiated 1 sternal tempements et . feel had been reasoved from the reacter vosoel.1-12 the failure had occurred later during feel handlias, the spent feel. p1 eeuld have been partially drained, a severe radiation -hasard could have been created by exposed fuel, and fuel integrity could have been joopardized by the loss of water.
2.
Descrintion of Plant Hatch equipment / activities as related to root document subiect(s1:
$ Plant Batch has ppeumatic seals in the Unit 1 to Unit 2 Fuel Transfer Canal, in the spent Fuel Storage Pool to Rea_ctor Well Gates and in the Dryer / Separator Storage Pool to Reactor Well Gate.
The Drywell to Reactor Well Bellows and Refueling Bellows are both flexible metal bellows with no pneumatic seals.
It ' should be noted we do not have Cavity Seals at Hatch.
inflatable bladder design Reactor 3.
Response to Applicable Recommendations: Recommendation 1: Ensure that plant design changes related to refueling operations are reviewed considering the full range of possible failure modes.
A failure modes and effects analysis should be performed as part of these safety evaluations where applicable.
Response to Recommendation 1: An offsite safety review is required for all safety-related DCRs.
This review considers the full range of possible failure modes.
Design changes related to refueling operations are considered safety-related per the " Plant Modifications Approval and Implementation" procedure (HNP-809).
ggg. 74 Ofy _.
.
_ ___ , e . . 50ER 85-1 " Reactor Cavity Seal Failure" Page 2 - Becommendation 2: Perform a design review to assess the plant's susceptibility to a loss of refueling cavity water.
As a minimum, the review should include the following: . , 3, ,- -4. the ability of.refueliag seals, mozzle dams, and main staan '- '.,,: ' Sl to sosist 3 sadden failure--This assessment should
- .;,,.7 * eM ee. plugsitinally 14hecider " the effects
'et '- everinflation, ~. - .. .. 4 y.; ;qQ et&mtlati egehetares " or otherTaschanisms ter-pressureJ] .xA , 4hermal' te,.misalignmeat*ded Ateselerance stackay, e Md?-14j7 ^4eisalC M 'Y p % 4- %d .- ... . ,... - , , ab,> '18entification -af all leakage paths which ,,"3 %. elange.sf :*he'.Acansfer 4: anal, tef ~ could resulte q -j .. ' ing . . end/or:. 41 < - ain-va g.. ~);. >< v.
g ., ieen$ese . epper M e 1s'gaakkefpban Desitiamed Ma iche(egfaeling eavity by . ement oc amailmslatism as an Aayat"tof4esign. reviews and . eseratpeasf... . tag. ; q,93.-~, g ~., p, ~
... , . f ...,. . 3' . ... . , ' meane to' Rem _ adat'ien 2: ~ ' ' . w c '.;- S1 phx.s - . -
T '. a. 'The tallowing seals and. plugs are used at Plant Batch: 2.. ' Refueling bellows 'l' hose age metal bellows, permanently- , - l installed, 'with welded interfaces.
As a secondary seal, i the bellows assembly uses a self-energizing spring seal.
These bellotas do not utilise pneumatic components and are not susceptible to failure due to overinflation, underinflation, or pressure loss.
They are also not susceptible to misalignment since they are permanently installed.
The bellows are not seismically designed.
- 2.
Bulkhead manways - These have 0-ring heads which are replaced each outage prior to use.
The reactor cavity is flooded about 1" above the hatches and an inspection for leakage is made underneath in the drywell prior to flooding the cavity.
These seals do not utilize pneumatic components and are not susceptible to failure due to overinflation, underinflation, or pressure loss.
The s hatches and hinges are of substantial construction such that misalignment is not expected to be a significant ' problem.
3.
Main steam line plugs These have a pneumatic seal and a - secondary 0-ring seal.
Therefore they are single failure proof.
The pneumatic seal is susceptible to failure due to overinflation, underinflation, or puncture.
The 0-ring seal is not.
Misalignment can be checked by opening drains in the main steam lines prior to performing work on the inboard MSIV's or safety relief valves.
These plugs are not seismi _ _ _ - _ _ _ _ _ _ _ _ _ _ l ' . . l SOER 85-1 " Reactor Cavity Seal Failure" Page 3 . 4.
The following gates all use similar pneumatic seals.
(a) U-1 dryer separator pool gate.
This is a single gate with 2 seals.
Both seals generally use the same air . supply.
- N..... a~. -
, . .,. , i.r.f. ?SQQM) W '1 feel 44**1 : gates. ? pse -ere~ gates with ope wifg.5#a- - - 1,.eacL*k Seth 'has M *geparate r line fe6 via'.3
- .h,W N arate.fegalater. peek.5 mech sphl' Ass a check valpe,.;f*
, . - 11e6 gt. 4:pN lalonnection W.,, '3 ' he r . . .
- -
m<. p. -- -w% ..s.. m w.- - , .., ,.F " T r '"*"JeVD-TDsk 9061.; Spent fuel racks have been insta11e8 ~. . ' lW
- 'la this 'locatlen.
The. gate sad. seals are ao longer f . - ' ..: L " t s..... c..
- n
- . . ,.QpSY;..,. a, ' - y'.t. Q; a .. ~q.
.; *. - ", . ..L 1 1-AreE2 . $ - .. . , ..,. .-.p:i -
' ;6y:.?' f-ey,_, b .. ' ' ' ' ~ ' ~ - ..: fers at 'M9Bhis jugenstats ' '*TT.fista is % :eeal W t - .. - . ... seals are sup$t.Who-Naive' . eame ' Meter.
naeWDham-joint. 411 7 mix 7. - c,,,...... ~ ::.
p1&ed Er ... .. , '.(f) 6-1 side transfer canai to U-2 eask poel gates - T.here - are 2 gates with 1 seat each. "they are generally only used during spent feel * shipments.
Generally both seals would be supplie8 by the same air regulator.
, . (g) U-2 side transfer canal to U-1 Cask pool gates same - comments as for (f).
(h) U-2 fuel pool to transf er canal gates - This consists . of
gates with
seal each.
Generally uses
regulator to supply both seals.
(i) U-2 fuel pool gate - This consists of 2 gates with 1 ' seal each.
One regulator supplies both seals.
(j) U-2 dryer separator pool gate - This is one gate with 2 seals.
Generally, one regulator supplies both seal, .
'. ~. . Ogc-q, " '\\ - SOER 85-1 " Reactor Cavity Seal Failure" k%s\\,/ Page 4 In general, pneumatic seals are susceptible to failure due to overinflation, underinflation, and pressure loss.
In all applications at Plant Hatch, at least one backup seal is provided.
However, both seals are generally supplied from the same air source, which. presents a mode of common failure.
Other than this, redundant. seals at each locaties'iwould ' resent a high degree of meliability, These. seals 1sre wof -
..$. gates and.their 'el'1%t is assure 8 '.the,gatas yg,y . , -Te larance. Jaformatiemina ': thermal end.se cost i .f~i."'y'g adily.evailable 4a Dkset 1 site..> c ,14 .
44maits has analysed '4he%emaition in whi 11,. mate a' s-r , -is.lest.
This includes a water level eyes erith f...
- d
. the transfer canal. rAvea.ander these.
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apert 1F. ' hv, ar7;c'1C 9esi p1; -p.:. eas.
trh 14, , . w _ l'* W "' & W, ensurias.9aths scie invan:.ble.h., f.
' .- g@. . d.Q4gQ . mithead StalmG p-zt%2,.9yn
m: y.
' Mis would drain'the;1reati tr'.4a4 , . , (, .7'.; ] 'has 3 manual valves'. ) It<1s a 3' line. { - 9.q,jKM; ' . . , ' 2.
Basin cavity / reactor - well drain This would drain the - reactor cavity and has 1 manual valve.
It is a 2" line.
3.
Dryer separator pool dre tu - Thil could drain the reactor ' cavity and f.nel pool if the propur cates were removed.
It has 1 manual valve and is a 2" line.
4.
Reactor vessel bottom head drain This has 2 manual - . valves and is a 2" line.
5.
Fuel pool cooling system - This system can take suction off the dryer separator pool and basin cavity drains.
There are several small loss paths, such as vents and drains, as well as a 6" discharge line to the CST and a 6" discharge line to the waste. surge tank.
There are also relief valves and the demineralizer drains.
6.
RWCU - This system takes suction off the reactor vessel.
Loss paths include relief valves on the heat exchangers, drains on the demineralizers, a 4" discharge line to the condenser, and a 4" discharge line to the waste surge tanks.
This system has a differential floor leak detection system which would alert the operators.
- -
l . U ! e - . SOER 85-1 " Reactor Cavity Seal Failure" Page 5 7.
RHR This system can take suction off the reactor - vessel.
It has a 4* flush line on the return to the reactor vessel which goes to the waste surge tank.
It also has relief valves and a minimum flow line to the j torus.
-8.
There is a 18. drain Eine between the 'thp1* De1 -gates.~,3t ' ~! ~
- &as leak det.ection instrumentation %.,
e3..pf? g,.;j ' . . .... - g- .. .. - , ...n- -- ...
- k*y?? - Q.. The fellowigger;9 Mesa gji y.>*
, .? .
- e
- .p' . .y. e ,; .y ..,. ~fV[ae ' . , -E
ate determinati 4., d.,' 4 ' - _ s .+ n .-
e, . 1.
In Secomber 1st 1983, 'the dose Kates-Sa'i ,
- meisters senpasster read steam udryer
- l
- . " 4t Ji istamoe.
. g'. '. Men. gI "
' < -
(~ j %:.:-, ~ ~4..'a -.<.3.te%i.dd.:.h ' ... %2 h= u ' ." .; . ' n Mansary 3.VS984.'-the.;Sese / tate - ' , .:c r.. .i . $g"rd.soparator amme les@ssisted bassa.ea:.$41 stance. 35tj'e in, - 7,s }. g: . m .: ~ '. . v.
a.
c-go < m a-w . ,. . , - 4.
5 3. +ct recent package 42 4 -eentrol ret' pped w s ' reading 23.000 R/hr.
Based on this,.en latividual blade is estimated to be about 10,000 R/hr.
~ 4.
Dose rates from LPEN's are u*nknown.
The only information available is that they are in excess of 1000 B/hr.
, Recommendation 3: Take the necessary design and modification actions to ensure that draindown of the refueling cavity and spent fuel Pool, such that . irradiated fuel is uncovered, is not a credible event.
Equipment and facilities should be capable, where practical, of minimizing damage and enabling and simplifying recovery operations.
The following actions should be considered: a.
Use of a seal design for which a catastrophic leak is not a credible failure mode.
b.
Modifications to the refueling cavity and spent fuel Pool, as necessary, to ensure sufficient water will remain to cool and Partially shield fuel assemblies in the upender, inspection stand, transfer tube, and spent fuel pool even if the reactor cavity seal fails or other credible, major leaks occu.
l ' . SOER 85-1 " Reactor Cavity Seal Failur,o" Page 6 ~ c.
Assuring adequate means for repositioning exposed fuel assemblies, such as remote control capability for the manipulator and spent fuel Pool cranes--Plants located in areas where severe seismic events are credible should also consider the availability _ of dependable, alternate sources of electric power for the cranes.
% ". 4 . '- 4. 4 revision af staras to indicate a reductie6htheisater level ... At the refueling eavity.and opent fuel peel ' .,.jp1 tir.aesittere er a medistien moniter/glassa;W ;esample, ,.'~.. .ea the-c sg enemipu]r,ter erane).
. ' e. -..
,- ,r e..Meevision et a means for isolating the speat.$wei.
1,.f roa a ;,,.. ad18.he setneling savity ofter -postulated - ~ egy, ' r y " ats y th ceasideratjes af predicatee '. g;g ' fk.'~4. * - s; ?3;w a.
v.
< LT,,, < sr 1 posse 4eiecnstentatteh,"E;. . 3- '*"l "- -
- $ty. -
. - - - ..- i
- g. Wee..Me eet etilise 'seale -ef the type thatpaapted 90ER.
"J . ';' .__. . '.W;m.$prewiting .y sepasste :str._eepplies te ^17 4esansguila -be 7- .c p ieered.
ceasideretten erill h givenp theMase gf mck __ g n,',; h alves and accumulators in these lines. gf...;- A3 . . w.
'b.
This design feature already exists at plant 1Eatek.
- c.
The design features at Plant Bantch should prevent Tuel from being exposed in a catastrophic accident, enlike the plant ,. i described in this SOER.
Therefore, this modification is not considered necessary.
d.
Fuel pool level alarms, fuel pool gate leak alarms, and refueling floor radiation monitors already exist at Plant
Hatch.
e.
A in the bottom of the fuel pools at Plant Hatch effectively isolate the fuel pool from the reactor cavity such that the fuel would not be uncovered in an accident.
Recommendation 4: Review refueling procedures to ensure that the following is accomplished: a.
Persons installing reactor cavity seals are provided sufficiently detailed guidance to ensure proper preparation / inspection, installation, alignment, inflation.
verification.
and testing prior to moving ifradiated components.
b.
Plants with permanent reactor cavity seals adequately inspect and/or test the seals prior to moving irradiated components.
i l
I l - . .
s - . SOER 85-1 " Reactor Cavity Seal Failure" Page 7 c.
The use of nozzle dans or main steam line plugs is restricted during refueling so that their f ailure would not result in a loss of the refueling cavity water while handling irradiated fuel assemblies.
a r/m.x.. .. Maintenance and eperations activities $ hat."could result in .- ', draining the transfer sanal, esfueling cavity, i.ted/or Spent 4 - nel pool. (sse receanendation 1Rb) are adeguate1_y ptrolled :str 4 g i ,,ecedures.
, ,7, p.., am . .1 %. ';',Q-gliYg..
- ...
. . .., , , . m .. , %., ,- %s& Limit the',aumber of fuel assemblies simultaneously susceptible ' .
MFMiG rto damage due to loss of refueling cavity. water, such as : .* 2, .? ' ial Asstrictions.ea refueling practices gg'.garse sd '. EM8' (A - - ' '. h.
. % Tn W t.;.,?
- i 1 *
.e l 2et.reteeling ureis :g 7,s deae
... ..n:. - i
- Dersp:%.-1 reaseea s,taviam-4shouel 2 g^y.,
p,
~ -qJ ~. ;3.. ? s'!;, ., :.,
OEatch '~4ees ' ~ - letable , .. a .-l: =. r design stor. ,yM Sygd
- .
__ vitY seals.
, ' g, -
- .j
. QG,9:- ,,.; >4 e.-gicfR,y,,4. ~ Plant .?" .g: r: t-
- .
. .- ... - - ' - Watch. utilizes. permanently installed Beactor Cavity Seals.
An investigation by Engineering to determine the inspection criteria and procedural requirements is being Performed.
.' - An initial visual inspection of the Reactor Cavity .,. ,.~ Seals will be performed during the Unit 2 refueling outage as Part of the Engineering investigation.
. . . c.
Plant Hatch utilizes main steam line plugs during refueling activities.
Discussions between Maintenance and Engineering . . are in progress to determine actions to be taken when the main steam line plugs are being utilized and an inboard MSIV is to be repaired or removed.
d.
All Maintenance Work orders are reviewed by the Shift Supervisor to assure activities would not result in degradation of plant safety, including draining of the Spent Fuel Pool / Reactor Cavity, e.
A maximum of 5 fuel assemblies can be simultaneously suspended during refueling operations at Plant Batch.
All applicable procedures instruct fuel handling equipment operators to immediately lower suspended fuel assemblies upon loss of Spent Fuel Pool / Reactor Cavity Water leve i ) ' i .
l - , i - SOER 85-1 " Reactor Cavity Seal Failure" Page 8 Recommendation 5: Energency and administrative procedures should address the following: _ a.
tamediate ' actions to. be itaken.4y.-crane ;ty.perators.
- refmeiers, and -ethera -in the sefwe' ling wort.$saa, Vower '.. ., ! " eastainment wavity.gspent feel pol.,and,Jether areas da case,et., aither na Wlow..erfp *@spid _ tal y@t
gj .e . mast.
'ti Mp 1tetsel f;& -- -- ~ cavity water" Revel--These4,pret.
4,l'ni- ! . - '4melade vacuation einstructions r and . _y wentainment and fmal building isolation l este . hf. ' ' .f I ,,..,.., .. .si'y,,,' '~ 'Qat.- l . - . $. spuidance for Jrewmaties..,ief Jperatessiva 7; 1,'.I?5.esttag ?,rece R1 '
r '.~- ! ' whe; aera ?. 15e8. access ten ~ ... ! f:,[h, + mt _f j ." f u e l.,p o o l,' - star r og ., _
- '.geoling subsystems.4Er.ar latae
. l ,. A- .u ( gwn[ vity and/or epeatJSpel ten.[ ' Z w '.. - -.. w:. '/ -
4.. sw:. - . s -rw s ;
- .
, k.%.. y $ Response to Recommendation 5:')a.3I. ',$ } $ " -. f p f.,[. p., ' 7 I ~ ' ' + c ..p w g.
. . y,..
_.
Emergency Operating Procedures.
BNP-1/2-1949, ? Decreasing ! Reactor Well/ Fuel Pool Water level," were generated due to j . IEB-84--03 to address the actions tirat must be taken in the event '
of a decreasing Reactor Cavity and or Fuel Fool 1 Water ' level.
, The procedures contain steps.that should be performed as conditions permit and continued manning of the refueling floor
is possible.
References were included in the Emergency ! Operating Procedures to discuss other actions to be taken I . depending on refueling floor conditions and area re-entry.
These referenced procedures are: HNP-1/2-1903, " Refueling Floor
Bigh Radiation" and HNP-4320 " Radiological Event."
Other . recovery actions must be planned on a case by case basis.
Recommendation 6: Training and pre-refueling briefings should be provided for al) ) Personnel involved in refueling activities.
As a minimum, such training should include the items listed inrecommendationj4 and 5. and the lessons learned from this event.
l
i i I .
i . . ' . SOER 85-1 " Reactor Cavity Seal Failure" Page 9 Besponse to Recommendation 6: Prior to refueling, involved personnel review the following { procedures: ' ... e.
< 3DEP-1/2-1903, *Refneling 71eet Nigh Niation" - .
, %k. ,. u.4.> . .. 7+', b.
.,,BIP-1/A-1931, " Irradiated Fm4'M9amage,During Bandling*.. e, p.t- . i
y ,,.g ong y, ,y c- .. . . c.
~ 3BIP-1/2-1949, * Decreasing ctor %11/ Fuel Pec1 Stater , Levela .;... . .- . g.& 'm. - 12
- ~*
. :-fe ,, ~. ' Aj ' .-g ' ' J.- Sitionally; e11..i;11oenesid.peese ev.- s
oeures malat m il 4bo'efma . . Q.
k'p)M'*_.,. . ^7M3 544,7
- k.p=E**Shel '
r Maa ~.1a the Alarch ,t' e
- licensed
. cjN '.
- 'l5l. c f th.? -S
'-h.:ik?ht:l7 % ' ' n~;sfM y.haeule for cearnletica 4f' &ctlean4:- M ' .. ;. : u ..j .
- .
m ".. n mi:.g-r, %... . " nI'emat6 sted at
- h Time of
. pfy,gy 34his Ressease: , g, g. - , q. ggy, ';,
- .;..
- . . --..; - , .c - . .a.
..... ~'. ~~ - . An update to this respetse will be issued by June 1.1985.
This update will provide the status af actions act completed at the time of this response.
Please contact C.
R.
Goodman at S-512-909 if you have any further questions concerning this matter.
- H. C. Nix General Manager
. HCN/SBT/C G/v12 xc: Manager of Engineering Manager of Operations Manager of Training Site QA Manager . Senior Shift Technical Advisor C.
R. Goodman Document Control (SOER 85-1) File (2) . -
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[ - _ ~ u , $* ! 'd 10101 1 *a so:st seeroegg eigg,1g _ g. g 33 y.;g, > ' ' l ~ . HATCH AIT SCOPE 1.
Determine root causes of initiating event.
(Operator closure of air supply valve) -gL Lac.
2.
Determine the cause of L;', F;;', Level Alarm Failure.
Determine the amount of water that was spilled from the Fuel Pool and how 3.
Isotopic contamination.
many gallons were released to the environment.
Determine licensese response to IE Bulletin 84-03 and IN 84-93.* .- 4.
, du N ' ' 5.
Determine Potential Risk in draining both fuel pools, Determine the potential for loss of secondary containment because of leak.
6.
7.
Determine licensee's knowledge of precursors of the event.
b Ed " ^ ^ *W r . . . ..
_ q
- . ,. i < .
. To: Reg. Conp.' - IEN OP. IEC RESPONSE FORM ( - n-9 Y '1 .,- -.,,.._,,_ wn s L n, c, . %,. rse . , - . . , . e, a. .- A ~ a f - A.;.,,0.7,'(f1 - ~ ~-m - . - a v L o / - > a. i e p r.k. p Q ' w ' - - -... .,. n pnv - - 6,@ Bh rz: -- - ,. . _..;.a .,. ~ - / -z.
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. ....... If len a eg++1=. r'rire-eHnns feeded: M ;ti . . ~ _ '
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.... ) _ Summary of root accument subject (s).
-. .... .. - - ~ .,. . , __. IE A/ M-93 en -,.-n ,o, +M ;- l taA 4' ~w C o +t o.eeGl.
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i ~ i Descriotion of Plant Hatch eouloment/ activities as related to root document subject (s): - 9/n,4-lle &,- / .)<~,<..- / n a e e s e,i n es l-le Tol /- i.> tJe (Aa'f 1 & '
1 f l - ! !- 7-c/ 7e r.,sf.e.,e Cei o / ~ ' , i r, t'J. e S,ne + faxc/ 5+ we, s Per / hk e s v j $A t*- O.0 h Q ff fs.y"L h@ *. As on h*Y l a./ Of YP N Y / $bt"> / 0L ;* Q
c' (./ i bo Sr ~ n,Y -f-rr. -- (Dn // 4 /- e. 7~l a bt v r, ie //^ $-h Weca.c 7%'v dA)b - - o ' A s //.. '., <>.] 'Eo,C, e /,', b //n,a -- i e.,, p.
/,, nt; Pfa; A fc> mes . ei k ' ///'a3.- ,,,, ' l-f, on < '7 Din eu & << fI e s' 4 :t b o . , The reason why this h,1 M, a problem at Plant Hatch: - - .1i /? o 1 * ft / 1 eL*) .O O Q4 />**4 0 O t'"t t ) en-=* / S h ~c'7 / e 1 "" / l f es/ h 13 # A &.c~Mb/s **S Y /3 $n l 3O A A 'i,h G S~ ain i a s.v! a //e i /, <- ,n d i,)a'bG/%. $t".W.c/ s selle Aer~ ) ' ,., r ^n '.,r% //e Y 7L n n/c~ f-eef k < s e s-e) /ea k's..e e hel- ! e n f If - rp<-/ llc //n.w Es 4 t e,0 "fc rat-y? 7t\\ , D/1
r t/ ' ' J
I .5 . . , i i 1 Description of actions that have been taken or will be taken: '! l--Gu d raod c$ eM v2lo'c $ wi// de.d e d e<f anAauer'a f o sk ues m eA /e+Mac e. l )le, A)ue s/ ce<//folleen A;/wr 4,f f ~ / a s 9.
Asp r e% tWr s r n s t o. //<A Ano, ain a sse AJo P m 2 A-R P sto-M
f f - rr i . r t e~ a he l,, o lu e. f/lAlb-Lk-1W9 Ndf-1. k- ?d$<hNrJA.% 2-24- / ' . -
-
o - - /O Asaside $n / o.2 des e es t Ore.d-los ~~ ... ' / - . . ....... .a Schedule for comoletion of any actions recuireo but not comolet' d at time of resconse: j . e ' O n 6 M9,u t HY . .s .... Q , .... -. -.. - - .....a; . . . . . . 's A 's L. .. - - - .- i o.
.... .. s...Xh.ha - . -. ..n r u,...,,,s 5 mew,,,,,,,,, - . ._.=_,mm._,__._s.....<.__ . k%k-6.k.&h.c~t$ 8 hmA~ LVGf kyn.
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C P-Ga..} + %.. CoAnt (7-410 H h 6} 4 - ' , ........ > . - Red-Com. fpprovali Acceptacle.. ,,.. ton-Acce.pt able---- -- . If' ten-Acceptatile,' Corrections teecec: . . ... - - - _ _.. _ - - ... .. , ...- , , . ..... .. AttEch AIT ano'IEN'or IEC - ... % . , . ..... -. 1.%.t."J - - '- * ihe,h-': ..... ...:... ... y ....
... .. ...... ..... ... . . ... . . . %
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G.ma % C~:,e Td Pumrt Avenue
Anan: r4 a LXe
twenore 40d $26 6526 ,
um =m DCL1 orface tioi ' 3%" g amia co., n 'd Georgia Power ' u. c n AUG 311984 ,,,y,m,,,..,.,, i ManaCet NucTar Enger'eer a,o cnes sww e n-+ee.'ng PLANIHAICH MANAGEMENT NED-84-469
August 29, 1984 PUNT HMUI UNITS 1,2 [//-M% IE Bulletin 84-03 Response (EITER # MG*A' N.! # - a /' / V - . Mr. R. A. Glasby ' Bechtel Power Corporation D' I ' ~ ~ '~ IJ~ ~ P. O. Box 607 y ]ffq ' 15740 Shady Grove Road ^U * Gaithersburg, Maryland 20760 RESP. MGR2
1 GM/DGM g MGMT: q Attached is IE Bulletin 84-03, refueling cavity water seal, which ( describes an incident at Haddam Neck and requires responses from licensees.
Please evaluate the potential for, and consequences of, a ) refueling cavity water seal failure,using the guidelines of the ..
- 4 i
bulletin.
Se bulletin rquires response within 90 days 'of receipt or
prior to refueli'ng, whichever is - sooner.
Given the current outage schedule for thit 1, please respond to the bulletin to this office by September 14, 1984.
Please contact M. J. Blackwood at (404) 526-7012 if . you have any questions.
Very truly yours,
kl4b /& , L. T. Gucwa w g I . Attachment xc: J.R. Jordan H.C. Nix, Jr.
Fo tA - 67 - 7 h D/S t ,
________-__ _ _ _ _ _ _ _ .% .
.,. @lb { WP ' D - i - SSINS No. : 6820 '
OMB No.: 3150-0011 i:UCtDR GENER;, TION ENG..,.-r.c..l?'c l Expiration Date: 04/30/85 i. c " IEB 84-03 g[g[q[ a qi r.
j UNITED STATES " ltiT1 @ A.T CCE Ci*:1 NUCLEAR REGULATORY COMMISSION ' , AUG 2 9 13( 0FFICE OF INSPECTION AND ENFORCEMENT l l . -,, -~ ~ ~ ~ ' WASHINGTON, D.C.
20555 f[$Ecf
August 24, 1984 V ' j , IE BULLETIN NO. 84-03: REFUELING CAVITY WATER SEAL Addressees: ' All power reactor facilities holding an Operating License (OL) or Construction i Fermit (CP) except Fort St. Vrain.
. Purpose: , The purposes of this bulletin are to: (1) notify addressees of an incident in which the refueling cavity water seal failed and rapidly drained the refueling
cavity, and (2) request certain actions to assure that fuel uncovery during refueling remains an unlikely event.
Description of Circumstances: On August 21, 1984, the Haddam Neck plant emperienced a failure of the refueling -
cavity water seal wi}h the refueling cavity flooded in preparation for refueling.
The refueling cavity water level (23 feet) decreased to the level of the
reactor vessel flange within 20 minutes which flooded the containment with approximately 200,000 gallons of water.
The seal assembly consists of an , annular plate with two pneumatic seals (Figure 1).
The assembly was recently redesigned by the licensee and had been used once previously.
The seal was manufactured by Presray, Inc.
The seal assembly was subject to a gross failure due to lack of an interference between the width of the seal annulus and the width of the opening, which allowed the seal to be significantly c'isplaced.
No fuel was being transferred at the time of this seal failure.
If, however, fuel had been in transfer at the time, it could have been partially or completely uncovered with possible high radiation levels, fuel cladding failure and release of radioactivity.
In addition, if the fuel transfer tube had been open, the spent fuel pool could have drained to a level which would have uncovered the top of the fuel.
Action to be Taken by Plants Currently in Refueling: 1.
Evaluate the potential for and consecuences of a refueling cavity water seal f ailure and provide a summary report of these actions by Augus t 31, 1984.
ECOS2 0358 ' l
.. . .. ... . ....._ .. ... . . .. . .-_ .s
i . .
. ,i IEB 84-03 August 24, 1984 , Page 2 of 2 ,, _ . Action To Be Taken By Plants Prior To Beginning Refueling Or Within 90 Davs , Of Receipt Of This Bulletin, whichever is sooner: . 2.
~ Evaluate the potential for and consequences of a refueling cavity water seal failure and provide a summary report of these actions.
. Such evaluations should include consideration of:gross seal failure; maximum leak rate due to failure of active components such as inflated seals; makeup capacity; time to cladding damage without operator action; potential effect on stored ~ fuel and fuel in transfer; and emergency operating procedures.
WrittenTeports describing the above actions shall be submitted to the approp Regiona1' Administrator under oath or affirmation under provisions of Section 182a,. Atomic Energy Act of 1954, as amended.
Also, the original' copy of the cover letter and a copy of the report shall be transmitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C.
20555 for - reproduction and distribution.
This request for information was approved by the Office of Management and Budget under a blanket clearance number 3150-0011 which expires April 30, 1985.
Comments on burden and duplication may be directed to the Office of Manage and Budget, Reports Management, Room 3208, New Executive Office Building, Washington, D.C.
20503.
If you have any questions regarding this ma Administrator of the appropriate NRC Regiona(ter, please contact the Regional - ' listed below.
l Office or the technical contact - , . ' h icha . DeYoung, Director ' , Offi f Inspection and Enforcerent Technical Contact: H. Bailey, IE (301) 492-7070 Attachments: 1.
Figure 1 } 2.
List of Recently Issued IE Bulletins ' !
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Ts9 . & _ M" "
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G - N . e l / a R e . . S L . r S[A e t a l l . y t iva - C - c i g t n - al i ma l ue e eS u n f P e j R h' kc % e [ i N GN ma A d d L . a
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