JPN-89-019, Proposed Tech Spec Changes Re High Pressure Water Fire Protection Sys.Supporting Safety Evaluation Encl
| ML20245D584 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/24/1989 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20245D578 | List: |
| References | |
| JPN-89-019, JPN-89-19, JPTS-87-014, JPTS-87-14, NUDOCS 8905010061 | |
| Download: ML20245D584 (7) | |
Text
- - - - - -. - - - - - - - - _ _ _ _ _ _ _ _ _,
l s
r;
-l l
ATTACHMENT I.TO'JPN 019 l
PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING HIGH PRESSURE WATER FIRE PROTECTION SYSTEM i
l (J PTS-87-014 )
1 l
\\
l l
-l l
t l
l l
1
)
New York Power Authority
)
JAMES A.
FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 j
DPR-59 l
8905010061 890424 l
PDR ADOCK 05000333 i
p PDC 1
m m
c e
n 1 s 6 s e
e n
e o
/h
/h t
t e
w m
et et s
s u
/
/
cn cn y
y c
e e
no no S
s e
c c
O m O m r
n n
e n
n F
O O
r o
o i
e i
i F
r t
t i
c c
e F
e e
h t
t t
e o
o g
t h
r r
E n
t s
f t
P p
G yi a
e o
rs Abt l
t f
e e
e yk T
a0 u e
o r
r t sc S
,r2 c l
c i
i a
e S e r
a n
y F
f wnh aI pti n
a t
oc S osc o
S l
i r
r ei nA ae i
M l
l e
e rt e oBd er t
h E
i i
t t
ucr nl a
s T
e b
a a
seu
,Ta n
r u
S S
v a.
W w
st s gS t o e
l T
Y r.
rs eos mE ga w
p f
N S
um em e
e rre uT n s o o
E S e pe r
r ppr p
i rel m
M N
t ot u
u p
Dt otf e
e E
O es s
s h e hE rf u v
t R
I y
h y ey n
s s
gr m cR a ng l
s I
T t
tS hS o
e e
iie aEt ti n a
y U
C i
t i
r r g Hf t EG simi V
S O
E l
on n
t P
pn E
T i
t o e
yo a
i R
O b
i v
fi c
h ht m R
a st i
i t i
a gs e E
P c
ec t
rc f
i i et C
i i e c
ee i
H HtI a
b c
d N
E l
l t e
vt c
A R
o po i
.o e
L I
p pr b
or p
L F
A AP O
TP S
A 1
I EV 2
R 1
P U
P S
4 NFA J
h r
m g - e e
e e
e l
e unh c
n p
r n
t na l moot iro i
o s
ou e
nb ori vei e
F i
y i nd r oarht ot est l
t S
t ani i rf t ct sdi arb e
c cmaf t e e
r rcea h
e n
e cpnrssim i s r t
t o
td er eooe ef r mfi e o
i onl e t
i t ev aeirp f
r t
r abt ont al l el t c o
o P
c p
aa r acwb ah as en e
crw p
u avt ypoe s
e t
eie hser wssib u
r o
rt pe et h end o t
t i
r i aor ri gt ponl yrao a
F P
f m u
i wn oiaf aett t
oes f
i g t
r ps S
e e
rtb s ek nh as rp d
N h
r eu e
rl aitl ees eee O
l t
i t al r ebt riovt l s r I
a F
a l p t a r wsl arb oi.
T n
f wd a arf e iawoah u D.
A
'S o
o r
ehh weof g v
r q
R M
i e
et s g p
s nr e,eh e2 E
E t
y t
r a i
eoeniobh rpcr1 P
T a
t a
uich r
l ap rt eoa O
S r.
i W
s ci ueb ril u l
ee3 Y
es l
soge sb at pocfk e v
R S
pm i
e es oh s
p r
onb ol n O
O e b
r r sl t el ad ntt i
t ao F
N t
a u
pa rl cnonnd r o vi t
es r
s no pa aioaaptd t
O S
I y
h y e
n s
hd ot hh t cr es nna N
T t
tS p
o e
gni h st eu dh d aoc O
C i
o i
r i atd g
ak b gyah e ii t
P h
aer i mpainh c r B. t f I
E l
on T
T i
t o e
e a
si ne h e l ri eai ai I
O b
i v
r.
c h
hpt gd t w t zd veu2 l c D
R a
st i
us i
o t miia es oesi rl q1 oe N
P c
ec t
sm f
i ounl e h yl hil aane s p O
i i e c
s e i
H B pi ah T sf td ayvor3i s C
E l
l t e
at c
R p
po i_
s e
G I
p pr b
oy p
N F
A AP O
TS S
A b
a.
I T
I 2
1 M
1 I
L 3
,l
i:'
3 ATTACHMENT II TO JPN 019 SAFETY EVALUATION FOR PROPOSED TEGNICAL SPECIFICATION CHANGES REGARDING HIGH' PRESSURE WATER FIRE PROTECTION SYSTEM (JPTS-87-014)
New York Power Authority JAMES A.
FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
l i
Attachment II to JPN-89-019 SAFETY EVALUATION Page 1 of 4 I.
DESCRIPTION OF THE PROPOSED CHANGES The proposed change to the James A.
FitzPatrick Technical Specifications revises' Specification 3.12.A.1.b, "High Pressure Water Fire Protection System," on page 244a as follows:
Replace Item b.
"...the water flow alarm device on each sprinkler, hose standpipe or spray system riser required to be operable per specifications 3.12.B and'3.12.D."
with
"...the water flow alarm device on each sprinkler, or spray system riser required to be. operable per specification 3.12.B and to each hose station riser isolation valve required to be operable per specification 3.12.D."
II. PURPOSE OF THE PROPOSED CHANGES The purpose of the proposed change is to clearly identify the hose station riser isolation valve as the boundary to the High Pressure Water Fire Protection System and to remove the reference that these valves are located near water flow alarms that are not and never have been a part of the system design.
A literal interpretation of Specification 3.12.A.1.b requires each hose station to have an operable valve downstream from a water flow alarm device.
The James A.
FitzPatrick High Pressure Water Fire Protection System has an isolation valve, but does not have a water flow alarm device associated with each hose station riser.
This change is purely administrative in nature and make the Technical Specifications consistent with the original system design as described in the FSAR and Fire Hazard Analysis Report.
Although this arrangement is not in complete compliance with BTP 9.5-1 (see Reference 3 for BTP 9.5-1 comparison against system design), it was reviewed and approved in the Fire Protection Safety Evaluation Report issued by the NRC on August 1, 1979 (see Reference 4).
In addition, the monthly surveillance requirements in specifications 4.12.A and 4.12.D ensure the t___
Attachment II to JPN-89-019 BAFETY EVALUATION Page 2 of 4 integrity of the hose station and riser.
.III. IMPACT OF THE PROPOSED CHANGES The proposed change to the Technical Specifications does not change any system or subsystem and will not alter the conclusions of either the FSAR or SER accident analysis.
The proposed change to the High Pressure Water Fire Protection System serves only to clarify specification 3.12.A.1.b to make it consistent with the system design, fire harard analysis and the FSAR.
The design of the High Pressure Water Fire Protection System includes water flow alarms on the water spray and sprinkler systems but does not include water flow alarms on the hose station risers.
This is in conformance with the description of the system provided in FSAR Section 9.8.
This proposed change resolves a QA recommendation to revise specification 3.12.A.l.b to correct the description of the High Pressure Water Fire Protection System boundary.
IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION The proposed change to the James A. FitzPatrick Nuclear Power Plant Technical Specifications involve no significant hazards consideration.
It is purely administrative in nature and provides a clarification to the Technical Specifications.
Operation of the James A.
FitzPatrick Nuclear Power Plant in accordance with the proposed amendment would not involve a significant hazards consideration as stated in 10 CFR 50.92, since it would not:
1.
involve a significant increase in the probability or consequences of an accident previously evaluated.
The 4
intent of the proposed change is purely administrative j
in nature to clarify the Technical Specifications.
]
There are no changes to setpoints, safety limits, j
surveillance requirements, or limiting conditions
{
for operation.
These changes have no impact on plant operations.
The changes will have no impact on previously evaluated accidents.
2.
create the possibility of a new or different kind of accident from those previously evaluated.
The proposed change is purely administrative in nature and is intended to clarify and improve the quality of the Technical Specification.
The change cannot create the possibility of a new or different kind of accident.
3.
involve a significant reduction in the margin of safety.
The proposed change is purely administrative in nature.
l i
)
l l
' Attachment II to JPN-89-019 SAFETY EVALUATION Page 3 of 4 and clarifies and improves the quality of the Technical Specifications.
This change-does not.contain any setpoint or safety limit changes regarding isolation or alarms.
The proposed change does not affect the environmental monitoring program.
This change does not affect the plant's safety systems and does not reduce l
any safety margins.
1 In the April 6,'1983 Federal Register (48FR14870), ' NRC published examples of. license amendments that are not likely to involve a significant hazards consideration.
Example (i) from this Federal' Register is applicable to this change and' states:
"A purely administrative change to technical specifications: for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature.."
The proposed change can be. classified as not likely to involve significant hazards considerations, since the change is purely
. administrative in nature and does not. involve hardware changes nor any changes to the plant's safety related structures, systems, or components.
The proposed change is designed to improve the quality of the Technical Specifications.
V.
IMPLEMENTATION OF THE PROPOSED CHANGE Implementation of the proposed change will not impact the ALARA or Fire Protection Programs at FitzPatrick, nor will the change impact the environment.
VI. CONCLUSION The changes, as proposed, do not constitute an unreviewed safety question as defined in 10 CFR 50.59.
That is, they:
- a. will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report;
- b. will not increase the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report;
- c. w31.1 not reduce the margin of safety as defined in the basis for any technical specification; and d.
involves no significant hazards consideration, as defined in 10 CFR 50.92.
Attachment II to JPN-89-019
~ !.'
SAFETY EVALUATION:
Page 4 of 4
.VII. REFERENCES.
- 1. James A.-FitzPatrick Nuclear Power Plant Final Safety Analysis Report, _
Section 9.8.
1.-James'A. FitzPatrick. Nuclear Power Plant Safety Evaluation Report (SER), dated November 20, 1972 and Supplements.
2.. James A.
FitzPatrick Nuclear Power Plant Fire Hazard Analysis,. Dated April 1977, Revised November 1983.
- 3. James'A. FitzPatrick Nuclear Power Plant Fire Protection Safety Evaluation Report, dated August.1, 1979
- _ - _ _ _ _ - _ - - _ _ - _ _ _ - _ _ - _ _ - _ _ _ _ - _ _ - - - _ - - _ - _ _ _ - - _ _ - _ - _ _ _ _ _ _ _ _ _ - _ - - _ _ _ - - _ _ - _ - _ - - _ _ - - _ _ _ _ _