ML18086A530

From kanterella
Jump to navigation Jump to search
Forwards Conditions for Facility Operation Above 5% Rated Thermal Power Which Have Been Completed & Confirmed Through Insps by Region 1
ML18086A530
Person / Time
Site: Salem PSEG icon.png
Issue date: 05/13/1981
From: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Sniezek J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8105220196
Download: ML18086A530 (4)


Text

'I l'

I l)Nl1TED STATES I NUCLEAR REGCJLATORV COMMISSION*

REGION I 631 PARK AVENUE' KING OP PRUSSIA,. PENNSYLVANIA 19406 MAY l 3 :1981.

Docket No *. 50-3"11

~..

~-~.

MEMORANDUM FOR;: J. H. Sniezek. Director. DRRRI>> IE FROM!:

B. ~- Gr1er, Director

SUBJECT:

.FUIJL POWER LICENSE CONDITIONS*- SALEM UNIT 2

  • Enclosed are those 1 conditions for operation above 5% rated, thermal power

.which:have been compJeted and conf;nned through inspections by Region I 1nspector.s.

The draft license was*presented at the briefing before the full Comnission

  • on Apr.11 28, 198l.. The spec1f1c:: items required and an inspection report :;

reference are included.

  • It is recomnended. that this update be forwarded.to tho NRR D1v1s1on of Licensing so tha~ the draft license may be appropriately modified prior to 1ssuanceJ

Enclosure:

As Stated.

cc:

J. Kerrigan;.NRR. DL :

G. Meye.ri1 NRR.** ml L. Norrholm, SRI: Sal'em

-~~rl~~

Boy H. Grier*

Directer *

.. 1

.... /,.

  • y.

, I

,,\\

,I*

~

./

___ J

~--.

I' I

Oocket* No *. 50-311 2.C.7..

2.C~lO.a.

.~ : i

. I

'~

2.c.(12)(a) 2-~.C.{12)(b)

.~::~

\\

z. c~ Ci'7) f FULL POWER LICENSE CONDITIONS SALEM UN11'. 2 Master; Equipment List Prior to exce*eding. five percent rated thermal :power, PSE&G wf11 '

have 'f.n place-a*complete Master Equipment List as detailed in correspondence to NRC' Region I dated June 3, 1980.

Comple:ted* - Reference IE Inspection Report No. so... 311/81-04 Environmen.tJ..1l.. QU~l.ifica!if>!t.(.S~.ctjp9.3. 1J.1. S4J?.P.1eJ]lent 5)

Prior to exceeding five percent power. PSE&G shall have fn place the procedural modifications described in the environmental qua1ificati.on submittal dated December 1. 1980

  • Comp1e.ted, - Reference IE Inspection Report No. 50.-311-81-05 Containment Isolation (Section 6.2.3, Supplements 4 and* 5)

Prior to exeeed1ng f1ve percent power.PSE&G shall 1nstall a reset alann for the containment purge and pt"essure - vacuum re1:ief valve reset circuitry.

Completed - Reference IE !nspect1on Report No. 50-311/81-10 Containment Isolation (Section 6.2.3, Supplement 4 an.d 5)

Prior to exceeding.five percent power, PSE&G sha11 align the isolation valves in the containment pressure - vacuum relief valves such that the maximum open position corresponds to 6Cil degrees.

Completed - Reference IE Inspection Report 50-311/81-05 Loss.of Non-Class IE Instrumentation and Cont\\"01 Power Bus Ourin*g. Operation (Section 7.9, Supplement 5)

I~

J.

I

/. '

~.

.\\*

PSE&G shall also provide the results of the ana1ysis and re'view.

of instrument: failure modes, in tabular fonn,.to the operators for use with existing procedures prior to operation above five percent powe~. *

.. ~~

-*/Completed* - Reference IE Inspection Report No. 50-311 /81-10

. - *2*~ C. (22) {a) i:

('.-

Sump 'Performa:nce (Section 6. 3. 3 2 Supp 1 ement 5)

PSE&G sha 11 establ 'fsh gu'f de 11 nes to ensure that an operator wil 1 be delegated the respons1b111ty of monitoring *the perfonnance of ECC system* during the rec.frcu1ation mode prior to operation above five percent *.power.

  • i'

-'.,\\

~.

Completed -*Reference IE Inspection Report No. 50-311/81-05.

.r

.r' I'

r

\\

  • /

12,.c. (22)(b).

I I

I 2.c. (24).(b)'(ii) *

  • .r.

2.. e. (24)(a)(iii) ii

,. I 2~c.o(25)(b)

I,

~

l,

-~~.

I

{

'I t'*.:

r~*

1' I

I.\\

i1,

.:1 t~\\:. (2S)(d) 1

/~~..

' ~.

\\

ll

. '?

2

      • \\.

'I j

  • " 1

.PSE&G shall e~tab11sh a. pbs1t accident 1og for recording 1ow.;.

pre:ssure injection perfonnance which, wi11 be included in the Emergency Duty Officer.ts Check Sheet prior to operation above..;

five, percent power.

1 Completed - Reference IE Inspection Report No. 50-311/81-05 category l Masonry Wal] s tss..cti on 3.8.3 1 Supplement 5)

'-1 t

. *J

'*i "f

Complete the wa11*capac1tystrengthening program or-remedial

    • -~

actions* described :in Section 3.8.3 'of Supplement 5 to the ~afety \\."

Evaluation Report.

  • /. ;i.
    • Completed - Reference IE Inspection Report No. 50-3'11/81-05..

~

I

. *i*.

. Confinn, that the proposed remedial actions do not preclude the, T1 option of implementing additional modifications which wou1c;i, if !

1 dictated by.future staff review. render the ma~onry wall design*~.

to meet: the: ze~o tensile stress requ.1 rements. under OBE and SSE

1 conditions.
  • -~'
  • ~.

Completed - Reference IE Inspection Report Nb. 50""311/81-05.

<",~ *.

e:.

Sho:rt...;Tenn Accident Anal sis and Procedure Revision Section 22.2:;I 1.c.1.,.

  • an,. *

"*.~

  • 11,

~

PSE&G shall revise the emergency operation fnstruct1on fn accordarjce with NRC co111nents on the reviewed procedutes prior to operation' )

above five percent power..

/r

Jl\\_.**.

Completed - Reference IE Inspection Report No. 50-311/80-16

"'*;(

ControI.J!,ooin Design Review (Section 22. 2*, I *.&ll

  • ':\\'

. PSE&G s1ha 11. complete the mod1 f1 cations to the emergency procedure~ *

  • prior to operation above five percent power.

}.

Completed... Reference IE.Inspection Report No. 50-311/81..,01 Tr:,aining for Mftigatfng Core Dama,se,.Cs~ction 22.2, 11.B.4)

PSE&G shall comp1ete the trainfng of; all operating *personne1 fn the use of 1nsta11ed p1ant systems to control or mitigate an accident* in which the core fs sev.erely damaged prior to operation above five percent powe*r..

Completed'

  • Reference IE Inspection Report No. 50-311/81-05

-~,

-~

i

.J.

I..

1 I.'

r*

r

1.

3

.2.c.(25)(e)(i) Auxiliar.y Feedwater System Reliability Evaluation (Section 22.2. * **"*.

II.E. L 1J I

PSE&G sha11 implement all surveillance and* operating pr'Clcedures detailed in Section 22.2, II.E.1.1 of Supplement Nb. 5 to the Safety Evaluation Report on Salem Nuclear Generating Station, Unit 2 prior to operation above five percent power *.

  • Completed: - Reference IE Inspection Repor-t Nos. 50... 311/80-18, 81 *01 and.' 81-06.

i*

j

  • ~
  • i

. r,.,.

..~;.

. I~

    • t

.. t...

  • . i.

4

  • *:{
  • =**

. ~-~.

~

-.. '":.1;

.1 *. *-

... ~

I

\\

" t',

~

J;;

§*

I *j

  • i

~

. ---~

. \\0 ~

  • 'I

'*{~ *.,

!'t *

.,-,j.

/";

  • .~;*. '

J

I