ML20236V749
| ML20236V749 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/23/1987 |
| From: | Gallagher J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Kane W NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8712070047 | |
| Download: ML20236V749 (7) | |
Text
g i
- ; ;h, i
PHILADELPHIA ELECTRIC COMPANY
,230P S'ARKET STREET
'?i.O. DOX 8699 PHILADELPHIA. PA.191U.
(215) 841 5001 i
JOSEPH M. G ALLA'eH E R 4
7
.Jl*.1.~.'J.*L"lo-.
November 23, 1987 Docket No. 50-277 i
50-278
/
.4 Mr. Willi m,2.
Kane, Director Division of Reactor Projects Region I U.S. Puclear Regulatory Commission
/
ATTN: 1.\\ocument Control Desk f
Washington, D.C.
20555 i
i.
i SUBJECP:
Peach Bottom Atomic Powar Station, Units 2 &'3 Compliance with 10,CFR 50 Appendix J for Valve Stem Pa::: king Testing and Additional Information in Response to Inspection Report Nos. 50-277/85-23
(
and 50-278/85-23
'J
REFERENCES:
- 1) Letter from J. L. Hankins (PECo) to K. R. Goller (NRC) 6ated August 13, 1976
- 2) Letter from S. L. Daltroff (PECo) to J. F. Stolz (NRCydated May 15, 1981
- 3) Letter from S. D. Ebneter (NRC) to S. L. Daltroff (PECo) dated July 29, 1985
//;
i
- 4) Letter from S.L. Daltroff (PECo) to S.
D.
Ebneter (llRC) dated August 28, 1985
- 5) Lecter from S. D. Ebneter (NRC) to S. L. Daltroff (PECo) dat2d August 15, 1986 E) Letter from E. J. Bradley (PECo) to H. R. Denton (NRC) dated October 10, 1986
/c
'l).1 Letter from R. E. Martin (URC) to Philadelphia Electric Company dated September 14, 1987 r
Dear Mr. Kane:
This letter is an amended response to our previous sresponse (Reference 4) to the Notice of Violation contained in Inspection Report Nos. 50-277/85-23 and 50-278/85-23 (Reference
- 3) and also represents a partial response on our valve stem packing testing program.
b f
B712070047 871223
[/
b
< 'PDR ADOCA 05000277
^ in PDR l'
Mr. William F. Kane November 23, 1987 Page 2 This response provides the necessary information for the closure of the Inspection Report Violation.
The Notice of Violation concerned the Type C testing of the valve stem packing of two containment isolation valves (AO-2520 and AO-2502B) in accordance with 10 CPR 50 Appendix J requirements.
This issue was also discussed in a meeting between the Nuclear Regulatory Commission and Philadelphia Electric Company held at the Peach Bottom Atomic Power Station on July 30, 1987.
A summary of this meeting is identified in Reference 7.
During this meeting, it was agreed that Philadelphia Electric Company would submit an amended response to the Inspection Report.
Our amended response and a partial description of modifications which provide for the testing of valve stem packings at the Peach Bottom Atomic Power Station in accordance with 10 CFR 50 Appendix J requirements are discussed below.
A description of the remainder of our packings test program along with the information requested per Reference 7 will be provided by January 20, 1988.
Violation:
10 CFR 50 Appendix J, Section III.C.1, requires in part that, " Type C test pressure be applied in the same direction as that when the valve would be required to perform its safety function unless it can be determined that the results from tests for a pressure applied in a different direction will provide equivalent or more conservative results."
Section III.D.3 and Technical Specification 4.7.A.2.f. require in j
part that, " Type C tests shall be performed at intervals no greater than two years."
l Contrary to the above, Type C testing performed on Torus j
Vacuum Relief Valve AO-2502B and Drywell air and nitrogen purge q
valve AO-2520 did not test the leakage boundary of the valve stem l
during reverse pressure testing performed on July 20, 1980, July
]
25, 1980, May 19, 1982, May 28, 1982, June 1, 1982, June 8, 1982, and July 14, 1982.
The valve stem is subjected to accident pressure and is required to perform a safety function.
The reverse pressure testing performed did not test the valve stem due to the specific valve orientation.
The containment integrated leak rate test was conducted satisfactorily on July 28, 1980.
Peach Bottom Unit 2 is considered to be in violation of this requirement only for the period July 28, 1982 to April 28, 1984, when the Unit 2 refueling outage was begun, since the containment integrated leak rate test satisfied the Type C testing requirement for the period July 28, 1980 to July 28, 1982.
This is a Severity Level IV violation.
Mr. William F. Kane November 23, 1987
)'
Page 3 l
l l
Admission or Denial of the Violation:
I Philadelphia Electric Company acknowledges the violation as stated and will comply with the Nuclear Regulatory Commission interpretation of the Appendix J requirements with regards to the potential leakage path represented by valve stem packings.
Reason for the Violation:
1 Failure to perform a Type C test in accordance with 10 i
CFR 50 Appendix J on the potential leak path, i.e.,
the valve j
stem packing, resulted in the identified violation.
Philadelphia Electric Company agrees that because of the configuration of the valves in question, the valve steam packing represents a potential leakage path from containment.
It had been our interpretation of Appendix J requirements that in cases j
where due to physical plant configuration it was only possible to i
perform Type C testing in either the conservative seat leakage direction or on the valve stem packing, the conservative seat leakage test was the preferred test.
Accordingly, when the valves (AO-2520 and AO-2502B) that were the subject of the violation were installed, they were installed to enable the conservative seat leakage test to be performed thus exposing the packing to the primary containment.
1 Therefore, the verification of the leak tightness of the i
packing would only be accomplished as a result of a Type A test.
1 Extent or Significant of the Violation:
This violation is significant in that failure of the 1
valve packing during an accident would result in an unisolable i
leak to the reactor building; however, the seriousness of the i
violation is mitigated by the periodic verification of valve j
packing integrity performed as part of the Type A test l
j i
Corrective Actions and Actions to Prevent Recurrence:
Philadelphia Electric Company has performed a thorough review of all primary containment penetrations at the Peach j
i Bottom Atomic Power Station to identify all instances where the l
inboard containment isolation valve is outside containment and where the packing on the inboard valve is exposed to the primary containment and is not tested in accordance with Appendix J i
requirements.
Of the 154 piping containment penetrations per i
unit, 80 penetrations have their inboard isolation valve outside containment.
Of these 80 penetrations, 8 penetrations have been identified that have containment isolation valves with untested
Mr. Willir.m F. Kann November 23, 1987 Page 4 packing and were not identified in our previously submitted exemption requests (References 1, 2 and 6).
Attachment I provides a detailed description of each penetration along with plans to resolve the situation.
Attachment I can be summarized as follows:
1.
Two of the 8 penetrations should have been included in the exemption requests previously submitted (References 1, 2 and 6).
These penetrations (No.
225 and 227) are for lines that terminate below torus water level and are continuously subjected to the head of water in the torus.
The penetrations wil'1 be included in a revised exemption request which will be submitted to the Nuclear Regulatory Commission by January 20, 1988.
2.
The six remaining penetrations contain containment isolation valves whose packing is not currently Type C tested.
Five of these six penetrations contain valves that are three inch or smaller.
Rather than perform special qualitative testing on these valves, block valves and/or test taps will be added to permit Type C testing of the packing in full compliance with Appendix J.
The remaining penetration contains the 20 inch Torus Vacuum Relief Butterfly Valve (AO-2502B) that was the subject of the July 1985 Notice of Violation.
Philadelphia Electric Company obtained written confirmation from the valve manufacturer that there is no significant difference in the sealing capabilities of the valve regardless of which direction the test pressure is applied.
Therefore, a modification will be performed to turn the valve such that the packing will be tested in full compliance with Appendix J.
The Drywell Air and Nitrogen Purge Butterfly Valve AO-2520 hat already been turned such that the packing will be tested in full compliance with Appendix J.
Our review has also identified a number of primary containment penetrations that have one of the following conditions:
1.
Small (under 2") manual block valves that are not containment isolation valves but are used to form the boundary for performing Type C tests.
2.
Small (under 2") normally open root valves on i
instrumentation lines.
l Mr. William F. Kane November 23, 1987 Page 5 3.
Vent, drain or sample element branches between the containment and the first (inboard) containment isolation valve.
We have not completed our review and/or field walkdovn of these penetrations to identify potential packing leak paths.
We will complete our review and provide by January 20, 1988 the information requested in Reference 7 regarding our plans for assuring the leak tightness of the valve packing during outages when Type A testing is not performed.
Prior to returning Units 2 and 3 to service, a Type A Integrated Leakage Rate Test will be performed subjecting all of the packing leakage paths identified in this letter to a test that confirms their integrity.
We will implement the modifications noted in this letter and perform Type C tests following implementation prior tc the end of the next outage on each unit in which no Type A test is performed.
Very truly yours, i
Attachments cc:
Addressee W. R. Butler, USNRC, Washington, DC T.
P. Johnson, Resident Site Inspector
]
R. Martin, USNRC, Washington, DC i
l l
1 1
1
Il
!{jl
-.7 s
5 3
5 5
e I.
t I
2 2
C E
4 4
4 4
oN I
1 2
2 TN E
H d
d C
l l
ae ae M
nr ne oi ol l
l l
eiu eiu l
l l
l l
l l
l 1
l l
l l
l l
vt q vt c l
l l~
l l
l l
l 1
l l
A u.
u.
- u. u.
u.
u.
u.
u.
u.
u u.
f f
f u
u u
l aie aie u.
hdr f
f f
f f
f f
f f
f.
f h.M e dr n
J J
J J
J J
J J
J J
nJ nJ n4 J
sAe f
d io n
n n
n n
n n
n n
n "J n
s n
t b
t' b
i I
i t
I ia i x ixi dd dd dd dd dd dd dd ed ed ed dd udl ud!
ix ix ix ix i x i n ix u
dd dd dd dd i
i I
i ix x
x x i x s
s I
i i
i di di di i
e
.l e
i en en en en en en en en en en en t n t n t n en aei cel ic t e t e t e t e t e t e t e t e t e t e t e se se se t e et w etw s
sp sp sp sp sp sp sp sp sp sp sp ep ep ep sp rt rt e
ep ep ep ep ep ep ep ep ep ep ep t p t p tp ep i s i s R
tA tA tA tA tA tA tA tA tA tA tA A
A A
tA nnn nnn r
r e
e e
oto oto f
eh eh eh eh eh eh eh eh eh eh eh bh bh bh eh it st t st o
bt bt bt bt bt bt bt bt bt bt bt t
t t
bt ai t i i I
l i
i i
i i
i i
i i
l i l i l i i mc r ne w
s s
w w
mc w
w w
w l
1 w
w w
l l
w l
l l
l w
l l
w l
w w
ne d
t l
1 l
l l
l l
l l
l l
i i
i l
l l
l l
eep eep n
c ie e
ie i e ie ie ie i
a e
wc lwc wc wc wc wc wc wc wc wc wc c
c c
wc ebn ebn e
ie ie e
we we we i
i e x es x e!
l f
n n
n n
n n
n n
n n
n sn sn sn n
G.
f ga ga ga ga ga ga ga ga ga ga ga ga ga ga ga ry ryi I
E nI nI nl n1 nl nl n1 n1 n1 n1 nl nl nt nl nl ladl adl g
i!
ii il i1 ii ii i1 i1 i1 if il ii i 1,ii aa imrs n
k mk mk o k ekcmk mki1mk aa ek mk m km k
y k m k
w k
v ieu eu l
c c
cr c r a
i c
c c r c
c c
k..
ao ao ao eo ac eo ao ao ao ao ao c-r c
mrs c
c-a ao pap a il i il i c
Pc Pc Pc Pc Pc Pc Pc Pc Jc Pc P c P
Pc 3 a.
S av S av P
e 2l g.
b nt i r s
sa t
tt s
t o t
t sp s
s is n
e ixf u
u ne o
t e
e UT i
d ef o
o t
o d
e e
n u
n g
n r
r r o l
d a
d d
d d
d d
d d
d d
nk a
eN o
m m
m m
m m
m n
m m
m ia n
n
- i/
s e
u t w e
o v
o o
o o
o o
o o
o
.o
.ul se e
e o
o e
R r
l r
r r
r r
r r
r r
r l
l t
t v
v i
i t e a
a a
a a
a a
a a
a a
pa, pgg a
a i
n S r.
d v
p a
a ann v v
r r
e e
e e
e e
e e
e e
e e
t e tii e
e rh d
v k
v la a
a a
a a
a a
sa saa o oa ws e
a o
l v
v v
v v
v v
v v
kk k
k.
x x
ec n
l c
l l
l l
l l
l tl tcc c
cp e e
a oe.
m v
v v
v v
v v
v v
v ev epp l
P l
l t tC r
n b
n n
n n
n n
n n
n n
t m t
mN itC t
t b
b iR R
t o
n
- cA c
r dp r
r r
r r
r r
r r
dr dse d
ds b
nN e
u da u
u u
u u
u u
u u
du det d
de uo uo imt R
T At T
T T
T T
T T
T T
AT AT s A At St St t
on
.t e
A vr nioa t t e
t n p
V V
V V
no y
B C
B B
8 B
B F
8 B
B CB CT TT C
TT T
BC T
G D
G G
G G
G B
G G
GG G
ho ct aed P e.
s e
oc tr "1
"1 "1
"1 "1
"1 "1
"0 "1
"1 "1
"2 "2 "2 "3 "3 "3 "1
"6 "4 6"
x S
2 E
1 sev lav 3
B A
1 0 8
9 Y
M Y
2 0
7D 44 3
47 5
s 0
0 0
0 6
1 6
0 0
0 0
40 49 44 1
e 3
5 3
3 7
1 7
5 3
3 3
23 22 22 5
34 3
v 1
2 1
1 1
1 1
2 1
1 1
41 4R 44 2
1 1 2
la O-0 N
A N
N N
N N
O N
N M
AN K
O OO O
DD O
AN MM A
MM M
v A
e t
y y
e g
s a
a r
g r
u r
r e
r d
d e
e e
t u
a p
p n
k u
n n
n n
n s
r P
h S
S r
a P
al al u
e n
x ey u
ey e
o o
ib ib b
a t
o i
e s
E t
t dl t
dl r
s yo yo r
r r
h an t
u n
n ap e ap B
u aP n aP n u
u u
x Wo it s
r e
e e
rp R
rp i
r r
r r
r T
T T
E y
o g
c r
Gu Gu
=_
o pdu pdu st u
i c
S T
r r
r S
e S
T S nt S nt C
C C
e ur S
u y
=
y ae ae P
i i
l I
I I
g r
t a
a t c m t c c
s R
s R
C C
C r
oS o
t t
ei ei
=
ut ut R
R R
u T
n n
f t a
ft V
r l
l l
r sg rsg t
t t
P p
y o
o ae S
aa l y oen oen E s
& s C s C u P
le1 le C
C t
v9 w
SmS Sn s
ml TTI TTi u
u u
s n
u u p
t t l l
I a I a I a u
Ca yp y
R R
Se C
Se r
I p
HHo HHo P x P x x
Ro Ch Ch Ch r
I t
e C
ru r
H H
On A Dn o
ru o
DS D
R R
AP C
AP T
DS RRC RRC HE HE N' E o
Cl P
T RC H
n le r
t e>
atr r t
C eN B
A B
A B
8 n
A B
D 2
5 S
I I
h 7
9 5
7
(
(!If
.s t
i.n 2 u3 tht iti non UbU rrr ooo fff ddd eee rrr iiiuuu qqq
.. eee 32 rrr ev tt eee iiggg la nnnnn V
UUaaahhh ooccc lo tt er l l l vt eeaaa n
uurrr lao qquuu VC e.
iiddd ve nneee yml v uuccc gal ooo l
f aVa mmr rr rr V
eeppp l l 1
eh e t pbe bbTTT 0
t aot ooRRR 7
uil a rrLLL 8
BDGG PPLLL 0
2 0
1
/
FVBT 1 2345 v
d BCGG n
D s
m e
e c
g t
/
e o
H L
N P