ML18046B046
| ML18046B046 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 11/09/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TASK-05-11.A, TASK-5-11.A, TASK-RR LSO5-81-11-012, LSO5-81-11-12, NUDOCS 8111130510 | |
| Download: ML18046B046 (6) | |
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Docket No. 50-255 LS0§ J} -
OJ ;;J Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Company 1945 W Parnall Road Jackson, Michigan 49201
Dear Mr. Hoffman:
SUBJECT:
SEP TOPIC V-11.A, REQUIREMENTS FOR ISOLATION OF HIGH AND LOW PRESSURE SYSTEMS REVISED SAFETY EVALUATION FOR PALISADES The enclosed staff safety evaluation report has been revised to reflect the arguments presented in your letter of July 3, 1981.
The staff con-tinues to propose modifications to the LPSI valve control circuits and additional safety analyses as a result of our safety evaluation of Topic V-11.A.
The need to actually implement these changes wi 11 be determined during the integrated plant safety assessment. This topic assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessmentsis completed.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
J As stated
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J} /1't See next page 8111130510 811109
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- See ~evious yellow for additional NRC FORM 318 (10*80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960
Docket No. 50-255 LS05 Mr. David P. Moffman Nuclear Licensing Administrator Consumers Power Company 1945 W Parnall Road Jackson9 Michigan 49201
Dear Mr. Hoffman:
SUBJECT:
SEP TOPIC V-11. A, REQUIREMENTS FOR ISOLATION OF HIGH AND LOW PRESSURE SYSTEMS REVISED SAFETY EVALUATION FOR PALISADES The enclosed staff safety evaluation report has been revised to reflect the arguments presented in your letter of July 3, 1981.
The staff con-tinues to propose modifications to the LPSI and SCS valve control circuits.
As a result of our safety evaluation of Topic V-11.A~ we are also propos-ing modifications to the eves valve control circuitry.
The need to actually implement these changes will be determined during the integrated plant safety assessment. This topic assessment may be revised in the ;future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessment is completed.
Enclosure:
As stated cc w/enclosure:
See next page Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing OFFICE ****** ~~~'-*****... ~.~:..~.=.?~.... ~.~-~-~.:.Y...... ~.~~-~.?.:.~.~-=-~~
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NRC FORM 316 (10-60) NRCM 0240 OFFICIAL RECORD COPY
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USGPO: 1981-335-960
Mr. David P. Hoffman
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'U?fi-~~;;'?p.r.:':-1.* Miller, Esquire U. S. Environmental Protecti-0n Agency.
- Isham,.Lincoln & Beale Suite 4200 :
Federal Activities Branch *. --*
One First National Plaza Chicago, Illinois 60670 Mr.' Paul A. *Perry*, Secretary Consumers* Power Compa*ny.
Region*v Office...
ATTN: EIS. COORDINATOR 230 South *oearborn s*treet Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michi~an 49201
.Charles Bechhoefer, Esq~, Chairman
.. :-*Atomic Safety and Licensing Board Panel Judd L..Bacc>'ri, Esquire U. S. Nuclear Regulatory Commission Consumers. Power.Company, "'*-C,., : *.*C -
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Great Lakes E1"1ergy.. Alli.ance 5711 Summerset Drive' Midland, Michigan 48640 Kalamazoo Public Library 315 South Rose Street Kalamazoo, Michigan 49006 Township Supervisor Covert Township Route 1, Box 10 1005 Calle Largo
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c/o U. S. NRC Palisades Plant Route 2, P. O. Box 155 Covert, Michigan 49043 Van Buren County, Michigan 49043 Office of the Governor (2)
- Room 1 - Capitol Building Lans*ing, Michigan 48913 Wiliiam J. Scanlon, Esquire 2034 Pauline Boulevard
- Ann Arbor, Michigan 48103 Palisades Plant ATTN:
Mr. Robert Montross Plant Manager Covert, Michigan 49043
SYSTEMATIC EVALUATION PROGRAM TOPIC V-11. A PALISADES TOPIC: V-11.A REQUIREMENTS FOR ISOLATIO!*i OF HIGH Aim LOH PRESSURE SYSTEMS
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I. INTRODUCTION Several*s.yster.is :that h~-ve a relatively lm*: design pressure are connect-
- e.d to the reactor coolant pressui~e boundc.ry.
-The valves that form the "interface *between the high. and low*pressure systems must have suffici-ent: i'edundancy and interlocks* :to -assure that the lD\\*i pressu.re systems are not.subjected to coolant pressures that exceed design limits.* The
~roblem is complicated since under certain operating modes (e.g., shut-
- down c6o1ing and ECCS injection) these valves must open**to assure ade-
- -cjlTate r-*e-a-ctor sa~ety.
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II. *REVIEW CRITERJA*
. I I l. RELATED SAFETY TOPICS AND IIHERFACES The sco~e of review for this topic w~s limited to ~void duplication of effort since sciT1e a*spects of the* re\\!ie1*1 h'ei*e perfor;::ed under related topics.
The felated topics and the subject matter are identified be-low.
Each of the related topic reports contain the criteria and review g~idance for its subject matter.
\\1-3 v-10.s*
VI-4 Overpressurization Protection RHR Reliability Containm~nt Isolation
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- Tcipic.~-11.Bis dependent on the pres~nt topic info~~ation for completion.
IV.
REVIEW GUIDELINES The review guidelines are ~resented is Section 7.3 of the Standard
-Reviel'I Plan.
- The RHR function for the PJlisadcs Plant
.Cooling System (SCS) i ~ uccomp 1 is hcd t-.1r the Shutdown
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,_. -; V:-.-~ EVALUATION J:s ~Jf;,;;g;rr -
As noted in EG&G Report l373F, the Palfsades Nuclear Station has three systems with a lower design pressure rating than the RCS that are directly connected to *the RCS.
The CVCS, SIS, and RHR systems do not meet current __
licensin*g requirements Jo.r_ isolation of hfgh and low pressure systems as specified* below.
- 1) *Th~ CVCS solenoid-controlled air-o~erated valves have no pressure-
. rel~t~d ~~terlocks, and the discharge line check valves have no position indication available in the control room as required by BTP.EICSB-3.
s*.':2y-.. The SIS -o*u-tboari -(farth:~st:~;f-rom.RcsY"'c_h.eck valves. in-thL~ i:i-nes:_
going-to the* RCS from:*the ilign=-an-d.lOw pressure injec.tibn:._pumps.::
are not testableJ and the motor-operated isolation valves in these lines.have no pressu_re-related interlocks as required-by SRP 6.:3.
An order was issued by the NRC on April 26, 1981, which requires that the. outboard check valve~ be leak teste~ a~the_l98l
- ,- **. ::' refuelfng*buta*ge-.'-~*:tlJ'e>.p1p-fog:must_be modified to permit-this-'at
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--- 3) None of the SCS system fsolation valves automatically close if RCS pressure i n*creas*es' -a6ove 5CS *system design pressure durfng -~
- SCSsystem op~ration, and the pressure-related opening interlock; are not redundant or diverse.
The basis for the staff posftions are:
l) The discharge piping of the CVCS is designed for full RCS pressure.
Since the valves are open with the system normally in service, there is no high pressure-low pressure interface at the air-operated valves or the check valves and the review criteria for this topic do not apply.
Consideration of gross failure.of a posftive displacement charging pump at the high pressure-low pressure interface is not within the scope of this topic since it is an extremely improbable event.
2}
The letdown line of the CVCS has pressure reducing orifices which would restri'ct flow from any break, the line has a pressure *relief valve protecting the line and the isolation valves close on low pres-surizer level.
I We find this acceptable protection against a break tn the 1 etdown portion \\of the eves piping*-
l **-
- 4) The SIS pumps and valves all receive a start signal at the same time.
It is possible given the failure of acheck valve in the**
low pressure path (Valve 3103, 3118, 3133 or 3148 LPSI) to over-pressurize LPSI via the HPSI system and lose som~ of th~ HPSI flow.
The staff agrees that sufficient information is available to.rletect leakage into the RWDS; With the exceptidn of the four items above the other issues raised in the licensee's letter of July 3, 1981 (attached) are addressed in the staff review of the systems required for safe shutdown and Topic V-:-11.B. :.. ~.
. :. *~ *,
VI. *= CON CL US IONS
- . Because the possibly severe consequences of a partial loss of HPSI flow
- or the concomitant damage to the LPSr system have not been analyzed,
_: ~the staff proposes that the 1 i censee:
C".~ f' -Demonstra't~ th~t,~dequate core cool in{can and the failure of a LPSI check valve.with valves_ fully open, __ of be provi d~d afte*r.,a LOCA the motor operated_LPSI b)
Provide a suitable pressure tnterlotk in the motor operated LPSI valves such that they will not 5e opened by a SIS. signal until the HPSI pumps have had time to come up to speed and the pressure in the piping common to the HPSI and LPS} is less than the LPSI design pressure.
Also, the LPSl valves should.be prevented from openin~
during valve testing if high pressure exists in the common piping.