ML20236J281
| ML20236J281 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 10/30/1987 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20236J284 | List: |
| References | |
| ULNRC-1667, NUDOCS 8711050245 | |
| Download: ML20236J281 (5) | |
Text
h}jyy G y.
n Etscruic g
+
1901 Grabot Sueet. SL Louis '
l l
J Oonald F. Schnell -
Vce Presdent l
October 30, 1987' i
U.S. Nuclear Regulatory Commission a
-Attn:
Document Control Desk
-]
Washington, D.C.
20555 l
Gentlemen:
ULNRC-1667 DOCKET NUMBER 50-483 CALLAWAY PLANT
-)
RESPONSE TO NRC QUESTIONS ON FIRE PROTECTION TECHNICAL SPECIFICATION AMENDMENT REQUEST
Reference:
1.
ULNRC-1447, dated 2/19/87 The referenced letter transmitted an amendment application request'to remove fire protection requirements from.the Technical
. Specifications and place them in plant-procedures and in the Final Safety Analysis Report.
j This letter provides responses to questions-based on
-j E
. discussions with the Nuclear Regulatory Commision staff concerning the amendment application..Since the submittal has been made under the lead plant concept, the-responses to the questions have the endorsement of-the Westinghouse Owners Group.
The enclosure contains.the questions and responses and revised portions.of the original submittal'.
The conclusions of the complete Safety Evaluation and Significant Hazard Evaluation
]'
transmitted by Reference 1 remain valid.
If you should have any further. questions, please contact us.
Very truly yours, Donald F.
Schnell l ~
JMC/pih D
' Enclosure is 8711050P45 G71030 '
(
PDR ADOCK 05000403 p
enn P(y j'
s Ly Isikng Artfross: 0,0. Box 149. St.1.ouis, MO 63166
n.
.%. s
,..nt.
a,-,
n.
hj,h e,m.
f i. ' ~ '.[
i i
1 m
m
(; s y n
.e u
.u
'~~
f
-i.
4
-! STATE.OFiMISSOURI )
.?
)-
LS-S l
W:
lCITYjoF'ST.. LOUIS.)
'o 1
L.
4
,i
. Donald'F.'Schnell,.of lawful-l age' being first duly sworn, L
L '2
'upon-oath.saysithat he;is Vice. President -Nuclear and an officer of UrsionLElectric Company;' that ~ he.has' read the foregoing document and '
knows the content';thereof;;that.he;has'ex'ecuted the same'for and'~on, L-behalf.of.said company,with ful1Jpower and; authority to do ao;'and i
-that.the facts therein? stated are true and' correct to'thelbest ofibis knowledge, information'and'_ belief.'
l
\\
By
/
Donald F.-Schnell
.o Vice President-Nucle ar,
u JSUBSCRIDED and sworn to'before me this'.34 k day of M ;, 1987 f
q BARBARAdhYAf NOTARY PD.BLIC, STATE OF Mf350URt
- MY COMMISSION EXPIRES APRIL 22, 1989 ST. LOUIS CC' NTY.
J l
1 I
l l
l.5
-l i
l l
(>.
'L 1.
J.'.,
cc:
Gerald Charnoff, Esq.
l Shaw, Pittman, Potts & Trowbridge 2300 N. Street, N.W.
Wa sh ing ton, - D. C.
20037 Dr.-J.-O. Cermak CFA, Inc.
4 Professional' Drive (Suite 110)
Gaithersburg, MD 20879 l
W.
L.
Forney
' Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road i'!
Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission l
RR#1 l
I Steedman, Missouri 65077 Tom Alexion (2)
Of fice of Nuclear Reactor Regulation l
U.S. Nuclear Regulatory Commission j
Mail Stop 316 i
7920 Norfolk Avenue 1
Bethesda, MD 20014 Ron Kucera, Deputy Direc tor
)
Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MD 65102
Enclosure to ULNRC-1667 a
1)
Confirm that deletion of the fire protection technical f
specifications will not affect commitments to Branch Technical Position APCSB 9.5-1, Appendix A and 10CFR50, Appendin R.
Response
The commitments to Branch Technical Position APCSB 9.5-1, Appendix A and 10CFR50, Appendix R are not changed as a result of this change request to remove fire protection items from the Technical Specifications.
These documents are addressed in FSAR (USAR for Wolf Creek) Appendixes 9.5 A and 9.5 E which are only being revised to include items which are being removed from the specifications.
Future changes to these sections will be made under the requirements of 10CFR50.59.
2)
The shutdown requirement of Specification 3.7.10.1 ACTION b l
should be retained in an appropriate commitment document, f
Response
1 As part of implementing the proposed revisions to the Technical Specifications, the requirements of Specification 3.7.10.1 ACTION b will be retained and will not be modified without prior approval from the Nuclear Regulatory Commission (NRC).
The requirements of Specification 3.7.10.1 ACTION b will be added to FSAR (USAR for Wolf Creek) Table 9.5.1-2 with a statement that no modifications to these requirements will be made without prior approval of the NRC.
3)
The site Fire Brigade requirement under the Unit Staff listing of Section 6.2.2e should remain in the Technical Specifications.
Response
The site Fire Brigade requirement will be retained in Hection 6.2.2.e of the Technical Specifications.
4)
Hcn will deviations from the fire protection program be handled with regard to deportability?
- Response,
]
After the relocation of fire protection system requirements from the Technical Specifications, events whien may be potentially reportable will still be evaluated relative to the criteria of 10 CFR 50.72, 10 CFR 50.73 and 10 CFR 21 on an individual basis.
A deportability determination will be nade based on this evaluation process.
Events involving significant degradation of the fire protection system would l
be reportable.
5)
Is your post-fire alternate shutdown capability covered by Technical Specifications and therefore in conformance with Generic Letter 81-12.
Response
Technical Specification 3.3.3.5 requires that specific remote shutdown monitoring instrumentation channels and the
]
auxiliary shutdown panel controls shall be OPERABLE with readouts displayed external to the control room.
The Bases for this Technical Specification states that, "The OPERABILITY of the Remote Shutdown System ensures that i
sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the facility from locations outside the control room and that a fire will not preclude achieving safe shutdown."
Since Technical Specification 3.3.3.5 covers instrumentation in addition to that required for safe shutdown in event of a control room fire, no modifications have been proposed to this Specification or its associated Bases.
6)
Confirm the accuracy of proposed FSAR (USAR for Wolf Creek)
Table 9.5.1-2.
Response
The proposed FSAR (USAR for Wolf Creek) Tabli 9.5.1-2 was provided for information.with the proposed inchnical Specification changes.
This table will be fcnalized to accurately and completely address all curres,.t Technical Specification requirements as part of the nSrmal FSAR (USAR for Wolf Creek) revision process.
1 i
)
._______________j