ML20148U060
| ML20148U060 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/26/1988 |
| From: | Johnston W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mroczka E NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| NUDOCS 8802030458 | |
| Download: ML20148U060 (2) | |
See also: IR 05000245/1987019
Text
,-
.
JAN 2 61988
Docket No. 50-245
Northeast Nuclear Energy Company
ATTN: Mr. E. J. Mroczka
Senior Vice President - Nuclear
Engineering and Operations Group
P. O. Box 270
Hartford, Connecticut 06141-0270
Gentlemen:
Subject:
Inspection No. 50-245/87-19
This refers to your letter dated December 8,1987, in response to our letter
dated September 23, 1987.
Thank you for informing us of the corrective and preventive actions documented
in your letter.
These corrective and preventive actions will be reviewed by
Mr. Dennis Kubicki of our Office of Nuclear Reactor Regulation (NRR) who had
'
raised these issues during the subject inspection (see Ur. resolved Items
,
87-19-01 and 02 in Inspection Report 50-245/87-19, for details).
By a copy of
,
this letter, these issues are being referred to NRR.
Therefore all future
correspondence on these issues should be addressed to NRR.
'Your cooperation with us is appreciated.
Sincerely,
Original 0icnC71
- -
r
William V. Johnston, Acting Director
'
Division of Reactor Safety
cc w/ encl:
W. D. Romberg, Vice President, Nuclear Operations
S. E. Scace, Station Superintendent
D. O. Nordquist, Manager of Quality Assurance
R. M. Kacich, Manager, Generation Facilities Licensing
Gerald Garfield, Esquire
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
HRC Resident Inspector
State of Connecticut
D. J. Kubicki, NRR/SPLB
'
'
,
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Decembe r 8,
1987
Docket No. 50-245
A06835
Re:
U.S.
Nuclear Regula tory Commission
Attn:
Document Control Desk
C.C.
20555
Gentlemen:
Millstone Nuclear Power Station, Unit No. 1
Response to Inspection Report No. 50-245/87-19
From August 17 through August 21, 1987, the NRC Sta f f conducted
an announced team inspection of Millstone Unit No. l's complia nce
The results of this inspection were
in a report
provided to Northeast Nueggr Energy Company (NNECO)
dated September 23, 1987.
No violations were identified
although two items, NFPA Code compliance for fire protection
systems a nd the fire ba rrier penetration seal program, remained
unresolved at the conclusion of the inspection.
The following
a re the results of NNECO's review of these items with planned
corrective actions a nd implementa tion schedules as requested .
NFPA Code Compliance:
(50-245/87-19-01)
NNECO has evaluated Millstone Unit No. l's complia nce with the
NFPA Na tional Fire Codes a nd has identified devia tions f a lli ng
into the following four groups:
(1)
W.
V.
Johnston letter to E.
J.
Mroczka , da ted Septembe r 23,
1987, Inspection Report No. 50-245/87-19.
l
7
/
T
.-
U.S. Nuclear Rsgulatory Commission
A06835/Pago 2
Decomber 8,
1987
.
.
1.
Code compliance deviations that can be justified as is and no
modification or action is required.
2.
Code compliance deviations that require surveillance
procedure changes or new surveillance procedures to comply
with the code.
3.
Code compliance deviations that are minor in nature and
require minimal resources to modify existing fire protection
systems.
4.
Code compliance deviations that require significant resources
to modify existing fire protection systems or add new fire
protection systems.
None of the NFPA Code complia nce items identified adversely impact
our ability to achieve and maintain safe shutdown conditions
following a fire, or maintain compliance with 10CPR50, Appendix
R.
In addition, all of the NFPA Code compliance devia tions identified
in Groups
1,
2 and 3 have no significant impact on the
ef fectiveness of the fire protection systems.
Any cha nges
resulting f rom the compliance items in Groups 2 a nd 3 will be
implemented before December 31, 1988.
Group 4 items have been broken into two areas.
The first area
consists of modifications to fire suppression systems, including
both water and gaseous systems.
The second area involves
modifica tions to fire detection systems.
It should be noted that
the specific deficiencies noted in the NRC Staff's inspection
report have been i ncorpora ted into thesa respective groups.
Modifications to the following fire suppression systems insure
that each system can ef fectively meet its designed purpose a nd
complies with the intent of the applicable fire codes:
o
Turbine Genera tor Bea ring Wa ter Spray System
o
Auxiliary Boiler Room Preaction Sprinkler System
o
Reactor Building Cable Tray Sprinkler System, North El. 14'6"
o
Reactor Building Cable Tray Sprinkler System, Southeast El. 14'6"
o
Machine Shop Sprinkler System, Fire Area T-7
Modifications to the following fire detection systems insure that
each system can ef fectively meet its designed purpose a nd complies
with the intent of the applicable fire codes:
-
_ _ _ _ _ _ _ _ _ _ _
,-
U.S. Nuclsar R3guletory Comminaion
A06835/P:go 3
December 8,
1987
.
.
o
Emergency Gas Turbine Generator Detection System
o
Main Generator Exciter Detection System
o
CRP 907, 903 and 908 Annunciator Panels
-
o
Reactor Building Elev. 82' Smoke Detection System
o
Smoke Detection systems reporting to Simplex Pa nnels 1-FDS-4,
5 a nd 6
o
De tection Systems in the areas listed below:
- Chemistry Laboratory
- MCC Area , Turbine Building Elev. 14'6"
- Reactor Building, I&C Hotshop Elev. 82'9"
- Screenwall Building
- Cable Vault Elev. 26'6"
- Hydrogen Seal Oil Unit
l
- Condenser Bay
i
- Diesel Generator Room
- Diesel Genera tor Fuel Oil Day Ta nk Room
- Auxiliary Ventilation Equipment Room
l
- Condensate Ta nk/ Pump House
}
- Switchgea r Area , Elev. 34'6"
- Makeup System, Fire Area T15A Elev. 34'6"
The above proposed modifications to the fire suppression and
detection systems will be evaluated in the Integra ted Sa fety
Assessment Program (ISAP) .
The results of this evaluation and
associated schedules will be i ncorpora ted into the next ISAP
update.
Fire Barrier Penetra tion Seal Prog ra m :
(50-245/87-19-02)
During the inspection, the audit team observed several fire
barrier penetration seal configura tions which appeared to be
beyond the size limita tions of the sealant as stipulated in the
Underwriters Laboratories listing and expressed concern with the
adequacy of NNECO's fire barrier penetration seal program.
recognizes the need for improvement in the fire barrier pene-
tra tion seal program a nd the eva lua tion a nd upgrading of the
program is a n ongoing process .
This evaluation and upgrade of the
program includes seal configuration adequacy, the development of
new procedures and the implementation of procedural changes as
s
required to ensure the proper implementation of the revised
program, and the complete mapping of fire barriers and their
associated pene tra tions.
The mapping of fire areas not located in high radia tion a reas a nd
the associated procedural or programmatic upgrades are scheduled
to be completed by December 30,1988.
The mapping of fire a reas
loca ted in high radia tion areas and the final assessment of the
program is scheduled to be completed by December 31, 1989.
_
D.S. Nucient Rsgulatory Commission
e
A06835/Page 4
-
Decemb3r 8,
1987
-
.
,
Concurrent with the mapping ef fort, the penetration configurations
will be recorded for review against qualified configurations.
Existing seal configurations which are not encompassed by a quali-
fled seal configuration will be evaluated on a case by case basis.
This evaluation will determine if the seal should be replaced with
a qualified seal or if documenting the seal with a Fire Protection
Engineering Evaluation is adequate.
Should several non-qualified
configurations appear to be similar in design, a qualification
test of that type of seal configuration will be considered.
Since
the scope of this seal qualification evaluation ef fort is unknown,
a preliminary completion date of December 31, 1989 is pla nned .
Should several qualification tests be required , the schedule may
need to be extended.
We hope that you find this information satisfactory, and we remain
available to answer any questions you may have.
Very truly yours,
NCRTHEAST NUCLEAR ENERGY COMPANY
pf
-
k b h
to
E.'
6toczP
Se
or Vice President
cc:
W. T.
Russell, Region I Administra tor
M.
L.
Boyle, NRC Project Manager, Millstone Unit No. 1
W.
J.
Ra ymo nd , Senior Resident Inspector, Millstone Unit
Nos.
1,
2 a nd 3