ML18081A600
| ML18081A600 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/26/1979 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 7911270314 | |
| Download: ML18081A600 (10) | |
Text
.. 0 PS~G*
Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 November 26, 1979 Director of Nuclear Reactor Regulation
- u. S. Nuclear Regulatory Commission Washington, D. c.
20555 Attention: Mr. D. B. Vassallo, Acting Director Division of Project Management Gentlemen:
LESSONS LEARNED SHORT TERM REQUIREMENTS NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 Public Service Electric and Gas Company hereby submits its response to your letter of November 9, 1979, which provided additional clarification of the NRC's short term Lessons Learned requirements.
The information contained in the attachment to this letter provides a detailed description of our proposed methods of implementation for those items where we are not in complete agreement with your requirements, along with a justification for the differences, as requested.
The attachment to this letter is applicable to both No. 1 and No. 2 Units of the Salem Nuclear Generating Station and is responsive to your concerns.
This information has been transmitted under a separate cover to the Acting Director, Division of Operating Reactors for the Salem No. 1 Unit (Docket No. 50-272).
Should you have any questions in this regard, please do not hesitate to contact us.
Attach.
The Energy People Very truly yours, jJ( /41-:;f-/;Hr_
R. L. Mittl General Manager -
Licensing and Environment Engineering and Construction o' q;f ~e-.. \\'
__ i
M P79 57 15/3 DISCUSSION OF ALTERNATIVES TO NRC STAFF REQUIREMENTS LESSONS LEARNED IMPLEMENTATION NOS. 1 AND 2 UNITS SALEM NUCLEAR GENERATING STATION
PRESSURIZER HEATER POWER SUPPLY (2.1.1)
Clarification 4:
An~ change-over pf the heaters from normal offsite power to emergency onsite power is to be accomplished manually in the control room.
Proposed Alternate:
The connection of the pressurizer heaters to a vital bus is made through a normally open Class lE circuit breaker.
This circuit breaker is mechanically key interlocked with the normal, non-vital power feed circuit breaker.
A manually\\
opened disconnect switch must also be closed to make the connection.
Once the connection pathway is established manually, the final connection of the pressurizer heaters to the vital bus (open/close the Cl~ss lE circuit breaker).is accomplished in the control room.
The setup of the vital bus feed to the pressurizer heaters can be completed in a time frame consistent with maintenance of natural circulation o*
The manual action of opening the non-vital supply circuit breaker prior to closing the vital power supply circuit breaker by mechanical key interlocks is necessary to eliminate any possibility of feeding other non-vital loads from the vital power supply.
M P79 57 15/4
- Salem l & *2
PI<ESSURIZER RELIEF AND BLOCK VALVES POWER SUPPLY ( 2.1.1)
Clarification 2:
The motive and control power for the block valve should be supplied from an emergency power bus different from that which supplied the PORV.
Proposed Alternate:
The design of the pressurizer relief and block valve arrangement for both Salem units was predicated on ensuring the ability to relieve.
This concept resulted in providing two parallel relief paths which are completely independent and redundant.
Such a design concept is necessary to provide protection for ATWS conditions and low temperature overp~essure transient~.
Incorporation of complete independence between the relief valve and block valve would negate the system's ability to me_et the single-failure criterion for the events identified above.
The e:xisting design, howGver / does incorporate the use of diverse_power supplies for the PORV's and their associated block valves.
The relief valves.are supplied by Class lE, 125VDC systems while the block valves use 230V and 115V vital AC.
There is no requirement for provisions to switch from normal power to emergency onsite power for these devices since the normal power supply in all cases is part of the onsite vital power system.
M P79 57 15/5 Salem l & 2
AFW FLOW INDICATION (2.1.7.b.)
Clarification B.l:
Auxiliary feedwater flow indication to each steam generator shall satisfy safety-grade requirements.
Proposed Alternate:
The Salem design incorporates auxiliary feedwater flow indication fdr each steam generator.
One flow instrument for each steam generator is provided.
In addition, three level instruments are provided for each steam generator.
The instruments are all powered from the vital buses, seismically qualified with environmental qualification for the level instruments 0hich are located inside the containment.
The present Salem design meets the NRC short term re~uirements.
The long term requiremerits for redtindant flow indication do not appear to be warranted.
Assurance of sufficient water being provided to the steam generators is of primary con~
cern.
Operator action is taken to maintain steam generator level rather than to assure a particular gpm flow rate.
This is accomplished by control of valve demand with steam generator level indication.
The use of auxiliary feedwater flow is not an absolute necessity.
Its loss will not affect the primary objective.
Present indiction of pump operation, valve demand/position, auxiliary feedwater flow (one/steam generator), auxiliary feedwater discharge pressure and steam generator level (three/steam generator) is ~dequate to meet the information requirements necessary to assure appropriate operator action.,
M P79 57 -15/6 Salem 1 & 2 i.
e 0 PS~G Public Service Electric and Gas Company 80 Park Plaza, T16D Newark, N.J. 07101 201/430-8217 Robert L. Mittl
. General Manager - Licensing and Environmen't June 30, 1981 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory CoIDlilission 7920 Norfolk Avenue Bethesda, MD 20014 Attention:
Mr. Frank J. Miraglia, Chief Licensing Branch 3 Division of Licensing Gentlemen:
REACTOR COOLANT SYSTEM VENTS NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 PSE&G h~reby submits,. in t'he enclosure to this letter, a description and procedural guidelines for the reactor coolant system vents in accordance with paragraph 2.c (25) (b) of Facility Operating License DPR-75.
Should you have any questions, do not hesitate to contact us.
Very truly yours, Enclosure CC Mr. Leif Norrholm
- senior Resident Inspector p
The Energy People
.. \\
I-
\\*
I REACTOR VESSEL HEAD VENT SALEM GENERATING STATION UNITS 1 & 2 NUREG-0737 ITEM II.B.l The reactor vessel head vent consists of a pipe extending from a part length CRDM housing to the Pressurizer Relief Tank (PRT) through a redundant grouping of solenoid vent valves.
The two attachments to this description show the schematic and the physical arrangement of the proposed modifications.
As shown on the schematics, the design has the potential of either venting to the containment or the PRT.
The part length CRDM selected for this application is the one nearest to the center of the reactor vessel hea.d.
The existing lead screw in t.his part length CRDM is removed prior to using it as a connection for head vent.
The connection from this part length CRDM cap (cap with a 0.815" diameter hole) is through a 1 11 Sch. 160 pipe connection.
This 1 11 pipe has a 11/32 11 diameter orifice close to the reactor vessel.
This pipe then runs to the PRT via a redundant grouping of solenoid vent valves as a 3/ 4 Sch. 160 pipe.
Break flanges are provided to allow the reactor vessel head removal and to p~ovide room for the manipulator crane movement~
The piping is supported to Seismic Category I requirements to ensure that allowable loadings on the part length CRDM housing are not exceeded.
The piping and valves are stainless steel.
This re~ctor vessel head vent is designed to meet the requirements of NUREG-0737.
This remote-manual vent can be actuated from the Control Room utilizing a key lock switch and will have power re-moved during normal operation.
The soienoid 6perated vent valves are powered from two.redundant Vital D~C. buses~
Open/close indications fbr the solenoid v~lve~ are provided in the Control Room, both visual and audible.
This reactor coolant system vent system size is kept below the LOCA definition size (3/8 11 ) through a 11/32" diameter orifice in the vent piping.
This will minimize the challenges to the Emergency Co~e Cooiing Sy~tem (ECCS) since an inadvertent opening of this vent would not require ECCS actuation.
I ".
-..... O'*.
l~* '~, ** *..
.,"1:;.
~*
f
_;..._:. <*~~.
~
I!'
I
~,,.
.. * '* ; ";';.;sN *
~
i I. ;J,,,i""
a B
- -~..i.-~c
~)*CoNTAlltl)ICT' ~~~.-:~*~
\\..c::.
l*I Uf.f!Jf$
~
[::ct{
- 131.'
I Dc:.c. I.
t=".c..
rcc4-.s-
~oQl~E'
- I..
"°C '4(]
R.,C. 41
,_\\l'~L'YOrr J.
.:.~.
~.. R,,.f:AclOt VESS~/.
"l~'IRC'r\\llU."t C~Sc!D
'Scc...cu+C)* o OP~~7tf/)
VEl'i"T.\\IALVE; *
'FC. -
~/It* I. &;:Q. c-~as e.J:J ARt::=A GNct R CLe.D
(_*
REPR.GSEN75 cl1AN~G..5F RG ~
Ut 42-E.D F c::l R I MPL.G /'Yt G"tf**rlNg Bem.o7c
\\f l'i N T I ti ~ CA P/j 13 J L. l 11,_
.; ~-
=~
.=crtl 1-~-+-~-~~*r°T~ o.;,s:.:-*
I <w~~f. l~~:w~~~-,~-~~~,c>.
~
I
- ,)*,,:,, ';"':.
. -~ *:
.:*l?.;~-f~
F&.1$
- . l :.- : ' :. l*<(~~;~..
~-
_ -TO GA..)
r-P"t;-:-~,.. '1~ ""~*
WI.' c* *,°WI.
.;; *':',, I
,,.. *37..... :.' ***::*
I. *1 1
- -*~ "
~:'.
- I n
. '10 LIQ L.-----~-----~~~"":\\?~~ WAs~*
. 'WLIL 1
.i
- r*~. *.:.
5 AbE;'VJ *-r ~2..
- RE.AC\\Olt 'lesse;c. HeAO
- 1.
-~.
V(?NT.. 5lt~T~M/ i
. \\
~.'
- .\\
. /
COOllNG ~HROUD
- I;i:;~t~I~,:
~-
f,~:'
RE~CTOR' VEi:,SEL.*'.*o.:<r:!~':i*"<\\i, A
- .. '; ** 1 y.
- ,*- \\i]:'.,'~+.~.l¢i ~;
- .. :)
..)'1°01'-.' COOLING
'illiROUD PORT!>*(4).
4 EL.111'* 107'**"
60.\\~"'M G...~Y\\~~-nn~ ~-\\C\\~~,
R~c;.:~~
.tteA.O.. __.. VE.NT Moor
~---
/
---. -;;;;;,_.,-~~"" Q\\hl<-0-"""" """',;;<.01_ I
(<?~) l W~l\\iS Zc/~/
"Zitt'/
~(I
- P-'17~
/t",,,?l't?
'Jit'P/7 J,YP/7
- e.l/b'Ml.7 Zi11"/
Z44'/
.:;u* P 7.?
,,.,.:?,, c?
J.IYP/7
~/,'9/7_
t
'. :. ' ~
- ~*..
._,A?#',,,r
_,,,,, 7~,,,r
.iA7#"A
- A71Y//
.IS"t?7.7
.N~IP
. ;r<??.:7
~,;i'dt?
IS"t??.7
.N.:P'~c?
.PS'Q7.7
.,.,...,,.di!?
'-'* *,,.,s )l'_;,p7-,,t:11 ;¥
µ S".)11.?t? 7-,,t_;r ;¥
, I~.#/ JA>>'/ FsVJ'/ ~/,
c:r;.>'77.7 A77P/ ~C?/V.i'A71"/I
~p
-'17.flYMV Zd~/
Zo'~/
.;?f P7.?
/t"_,?/t?
~~9/7
~,¥~/7 t
.:I'"" 7,-,;f i',;17,,.,,,,,
,;.>t??.::>
/t"';P#t?
.P.5"1?7.::>
- V..P'#"'t?
,,,M,r ;v.?'77*/l.T,,:Y zo
¥h/JAf(J) t
.i'S"C'7.7
/!',,?/(?
MS :0"7*PA'