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Meino to Files (50-219)
THRU:
nnis L,1.Ziemann' L
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.on.,4w.w~, Chief, Operating Reactors Branch #2,f
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-MECTING WITH JERSEY' CENTRAL POWER AND LIGHT COMPANY ON OYSTER CREEK ISSUES e
On February 21, 1974, a meeting was held'in Bethesda with representatives of the Jersey Central Power and Light Company (JCPL) regarding the following issues relating to the Oyster Creek facility:
1.
Augmented off-gas system 2.: Explosions in the off-gas system 3
Outstanding items for the FIOL 4.
Expected changes to the Technical Specifications prior to issuance of the FIOL A list of the treting attendees is attached. The results of the meeting are surnsrized below:
1.
Augmnted off-gas system A discussion cf the JCPL subn.ittal dated Septen17er 20,1973,
" Description of Proposed Modifications to the Liould, So2id and Off-Gcs Radioactive Waste Systems for the Oyster Creek Nuclear Generating Stations" strmiarized our findings that the present design results in offsite doses in excess of 5.0 Rem if a rupture in the off-gas system occurs due to the Safe Snutdown Earthquake (SSE). On this basis JCPL proposed to submit a reanalysis and redesien that would limit deses to not greater than 5 0 Rem under the condition postulated. Tne discussion centered around Regulatory Guides 1.26 and 1.29 and the possibility of a hydrogen explosion in the codified system. Results of the accident analysis perfomed by the Regulatory staff were displayed in tabular form, shown below,
-to identify doses resulting from fai]ure of various parts of the off-gas system at various release points.
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9604170105 960213 PDR FOIA DEKOKT5-258 PDR
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. Equipment
A00 Dose (EM)
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SJAE.
.'25 2 5-(1 hr. isolation) 25 or or or SJAE' O.42 0.42 0.42
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-isolation)-
-(2 hr. release).
1.48 1.48 Delay Line Charcoal Beds #
6.14.
0 (2 hr. release)-
- Seismic I'A00 Bldg. and A00 system 7B-Turbine Bldg release poir.t
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A00 - A0G Bldg. release point
- Seismic I A0G Blds and-A00 System with delay line proven for OE by dynamic
.. analysis.
The total dose from columns 1 and 2 is 8.04 to 10.12 REM depending on th.e isolation time of the Steam Jd; Air Ejector (SJAE)-
7he total dose from column 3 is 1.9 to 3 98 REM and the total dose from column 4 is 0.42 'to 2 5 RD4 depending on the SJAE isol.ation time.
The assumptions used in the Regulatory staff's calculations are as follows:
Release rate 260,000 cc /sec
=
2.3'x 10-3 sec/cm3 X/Q (Turbine Bldg)
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4.6 x 10-3 sec/cm3 X/Q (A0G Bldg)
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-100% release of gases from charcoal beds
. - Total' beta, garma dose 60 minute delay for delay line holdup
.. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> release period from charcoal beds and delay line -
SJAE isolation t$1nes of 10 minutes and 60' minutes From the above table it is evident that the proposed off-gas system when subject to the SSE is not adequate to limit doses to less than 5.0 Rem at the site boundary.
Corrective measures require at least a Seismic' Category I design' for the Augrentea Off-Gas (A0G) system and building to meet the accident dose limit requirements for operating plants specified by the Regulatory staff.
2.
Explosion in the off-gas system
'The Regulatory staff!s analysis of doses at the site boundary resulting from the explosive reccnbination of disassociated-hydrogen and oxygen gases indicate that the dose could exceed 0.5 Rem. The calculated dose at the site boundary would be 2.5 Rem for a onc hour release at ground level, recognizing that the turbine building exhausts at roof level and that the SIAE isolation valves may not be safety grade.
Isolation valves of safety grade quality, i.e., Quality Group C without N stamp and material certification, would.be required to assure-SIAE isolation. The' dose at the site boundary due to an explosion in the off-gas system would not exceed 0.5 Rem if closure of safety grade SJAE isolation valves occurred within 10 minutes of the incident.
If safety grade isolation valves are not installed, the system could be isolated by closure of the main steam isolation valves. Appropriate administratite measures and means to inmediately detect rupture of the off-gas system rupture disk are required to restrict the dose under these conditions.
-3. L Outstanding Items for the FIOL l'Ibe following list of items required for the Regulatory staff review were discussed and dates JCfL expected to submit each item were established as shown:
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I4-April 9, 1974 JCPL Submitbal Dates Outstanding Items:
f (1) Vacuum Breakers 3/29M4 i'
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(2) -Emergency Plans
.2/25/74
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l (3) l' Personnel Qualifications 3/29M4-l (4) High Energy'Line Break 3/29/74 (5) Rod Worth-3/1/74
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(6) Rod Worth Minimizer Tech.' Spec, Change 321M4 (7) ATRS 10/74 (8) : Pipe Break Inside Containment 3/1/74 (9) On Site Radiation Protection.
2/25M4
~ (10)' EI&C ques. Sb & Sd in our 1tr. of 7/3M3 3/1M4 (11) EI&C ques. Se in our letter of 7/3M3 3/1M4
'(12) Fracture Rughness, Primary System' 4/1M4 (13) Leak Detection System unknown (14) Coolant Chemistry 4/1/74 (15) Comparison w/ Regulatory Guides 9 by 3/4M4; remaining 10 (19 outstanding)
'by 3/29M 4 (16) Flood of Equipment Important to Safety submitted (17)ECCS 8/6M4
'(18) b rus.
unknown (19) A00 System-4/15M4 1
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-5 April 9,197,4 Mem.
14. Expected Changes to the Technical Specification Prior to Issuance of the FIOL
'Ibe extent of expected Technical Specification changes were.
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' discussed in general. -It is expected that JCPL will nnhmit a-list of areas for which they propose to request changes. The
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Regulatory project manager win also prepare a nst or the-changes he considers appropriate. These items will be discussed in detail at future meetings.
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John I. Riesland Operating Reactors Branch #2 Directorate of Licensing cc: Donald J. Skovholt Dennis L. Ziemann Tin ms J. Carter John I. Riesland.
Reba M. Diggs 000 R0 (3)
Jersey Central Power & Light Ccmpany l
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