ML20073K582
| ML20073K582 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 04/14/1983 |
| From: | James Smith LONG ISLAND LIGHTING CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, SNRC-863, NUDOCS 8304200362 | |
| Download: ML20073K582 (52) | |
Text
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _
=q SHOREHAM NUCLEAR POWER STATION 3
P.O. BOX 618, NORTH COUNTRY ROAD e WADING RIVER. N.Y.11792 w w--
Direct Dial Number April 14, 1983 SNRC-863 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission Washington, DC 20555 Requirements for Emergency Response Capability - Implementation Schedule Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322 Referemce:
Supplement 1 to NUREG-0737, Requirements for Emergency Response Capability (Generic Letter 82-33, dated December 7, 1982)
Dear Mr. Denton:
Enclosed is LILCO's response to the reference letter and its enclosure.
This response provides LILCO's current schedules and a description of our plans for implementation of NRC requirements for Emergency Response Capability (ERC) as outlined in the above referenced letter.
This information was required to be submitted to the NRC by April 15, 1983.
The following items constitute the submittal package:
5 Attachment A - Safety Parameter Display System (SPDS) pC Attachment B - Detailed Control Room Design Review (DCRDR) i Attachment C - Regulatory Guide 1.97 Rev. 2 (RG 1.97) -
y0 I
Application to Emergency Response Facilities (includes a report describing Shoreham's compliance with RG 1.97)
[p D,e Vl "'{ g Attachment D - Upgrade Emergency Operating Procedures (EOPs)
Attachment E - Emergency Response _ Faci.lities Attachment F - Integrated Schedule for Emergency Response Capability Attachment G - Shoreham Regulatory Chaage Planning Schedule Attachment G has been included based on discussions held between the NRC and LILCO at a meeting on March 23, 1983.
This attachment delineates LILCO's plans for implementing regulatory-required post-fuel load modifications and identifies B304200362 830414 PDR ADOCK 05000322 F
(_
SNRC-863 April 14, 1983 Page two regulatory required modification activities beyond the ERC scope in order that your review of Shoreham's schedule may take into account work loads involving other areas.
L'ILCO plans to integrate the design of the SPDS, implementation of RG 1.97, DCRDR, plant specific EOP's, and operator staff training using a common, event-based analysis technique.
In accordance with the recommendations of NUREG-0737, Supplement 1, LILCO will conduct a task analysis of the emergency operating procedures that will simultaneously serve to drive:
o final, plant specific EOP validation o
DCRDR o
verification of SPDS parameters o
integration of Reg. Guide 1.97 changes o
design of training and staffing By simultaneously referencing each of the above items to the plant specific emergency event base, the integration required in par. 3.1 of NUREG 0737, Supplement 1, will be achieved.
Generally speaking, the DCRDR/EOP/RG 1.97 integration will be based upon an analysis of workstation and manning requirements.
-This analysis will make reference to real plant response time information that has been generated by the development of plant specific EOP's, as discussed in Attachment D.
The development of training requirements will be driven by the same, real-time event base.
The analyses that will be conducted to achieve the desired integration will, where feasible, be conducted in parallel.
This approach will allow the various items (DCRDR, EOP's, SPDS, training and staffing) to be iterated against each other.
The result of such iteration will be the optimum resolution of human engineering issues within the limitations which are inherent in control room design.
[
SNRC-863 April 14, 1983 Page three
.LILCO is' proceeding based on the information and' schedules noted above, and. trusts that this information satisfies NRC requirements.
Should you have any questions, please contact this
" office.
Very truly yours, J. L. Smith Manager, Special Projects RWG/spg Attachment cc:
J. IIiggins All Parties Listed in Attachment 1 6
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ATTACH."ENT 1
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Lawrence Brenner, Esq.
ilerbert H.
Brown, Esq.
Administrative Judge Lawrence Coe Lanpher, Esq.
. Atomic Safety and Licensing Karla J.
Letsche, Esq.
Board Panel Kirkpatrick, Lockhart, Hill U.S. Nuclear Regulatory Commission Christopher & Phillips Washington, D.C.
20555 8th Floor 1900 M Street, N.W.
Washington, D.C.
20036 Dr.' Peter A.
Morris Administrative Judge Atomic Safety and Licensing Mr. Marc W.
Goldsmith Board Panel Energy Research Group U.S. Nuclear Regulatory Commission 4001 Totten Pond Road Washington, D.C.
20555 Waltham, Massachusetts 02154 Dr. James H. Carpenter MHB Technical Isssociates Administrative Judge 1723 Hamilton Avenue Atomic Safety and Licensing Suite K Board Panel
-San Jose, California 95125 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
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Stephen B.
Latham, Esq.
Tuomey, Latham & Shea Daniel P.
Brown, Esq.
33 West Second. Street Attorney R.O. Box 39S Atomic Safety and Licensing Riverhead, New York 11901 Board Panel U.S.
Nuclear Regulatory Commission Washington, D.C.
20555 Ralph Shapiro, Esq.
Canraer and Shapiro, P.C.
9 East 40th Street Bernard M.
Bordenick, Esq.
New York, New York 10016 David A.
Repka, Esq.
U.S.
Nuclear Regulatory Commission Washington, D.C.
20555 Matthew J.
Kelly, Esq.
State of New York James Dougherty Department of Public Service 3045 Porter Street Three Empire State Plaza Washington, D.C.
20008 Albany, New York 12223 m
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ATTACHMENT A-SAFETY PARAMETER DISPLAY SYSTEM In accordance with our previous submittal regarding this issue (Ref; letter SNRC-820), LILCO is presenting herein our implementation schedule for SPDS " Phase II" -(Attachments F and G).
To enable ready interpretation of the schedule, the ensuing
-paragraphs _will provide clarification, metho o ogy, status, and dl justification.
Shoreham Phase I SPDS is completed for its intended " Interim Only" function, as referenced above, and will not be further detailed herein.
.Shoreham Phase II SPDS is therefore the basis for the submittal on Generic Letter 82-33.
The Phase II SPDS, hereafter identified as SPDS, has been designed in accordance with NUREG-0696, and, as such, is an elaborate computer-based system with a material cost in excess of 5 million dollars.
In order to address the implementation of SPDS in a logical manner, it is necessary to understand the magnitude of the S?DS, the construction impact of the SPDS, and the method.of supporting completion at an NTOL/OL facility.
The SPDS for the main control room will be of seismic design for the computers (two) and CRT displays (two).
Power supply will also be seismic via uninterruptible power supplies (two). This seismic design represents a substantial upgrading beyond regulatory requirements.
The SPDS will be displayed in the TSC (3 CRTs, 1. printer) and also the EOF (3 CRTs, 1 printer).
The TSC/ EOF displays will be driven via non-seismic conputers (two) and powered via one uninterruptible power supply.
The existing data base. consists of appronimately eight hundred inputs selected from Regulatory Guide 1.97, Regulatory Guide 1.23, and other Shoreham systems as necessary.
The SPDS will be displayed in three levels (I-Preventive, II-Diagnostic, III-Mitigative) consisting of thirty-one displays, total.
The computer software is currently undergoing vigorous verification and validation processes to ensure the accuracy of module development and integration.
The entire computer system (hardware and software) will undergo tasting at the factory, and again after installation l
at the site.
Inputs for these two testing sequences will be via i
micro-computer simulation.
Subsequent to computer system integration with the multiplexing system and the field sensor inputs, the system will be final tested by the Startup organization using actual plant parameters.
To enhance a plant's design and capability by use of this system, as described above, entails a tremendous construction / testing
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l impact.
To obtain signals in support of system design requires (in addition to that already completed) approximately 144,000 feet of cabic, 15,000 feet of conduit, 30,000 man-hours of design, and 55,090 man-hours of installation followed by I
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L
l ATTACHMENT A - Page two.
associated testing..The above numbers are representative of the defined post-fuel load work, some of which has been' initiated prior'to fuel load.
Various degrees of difficulty are experienced in such an endeavor and, comparatively speaking, may_
be classified as follows:
CP Easy NTOL -
Difficult Extremely Difficult OL Progress has been made to date regarding field work for parameter inputs; however, much work remains.
Work had proceeded during the CP phase but was halted in the latter part of the NTOL phase as necessitated by plant testing and fuel load programs.
This was cited during LILCO's presentation on November 19, 1982.
(Refer to letter SNRC-820, dated January 17, 1983).
Currently, Shoreham is developing an intensive post-fuel load modification program.
This program will allow issuance of-detailed, comprehensive design implementation packages for each of the numerous modifications currently identified.
This
" package concept" will allow modification work to proceed during operation, with the added benefit that when unscheduled outages of sufficient duration occur, packages will be ready for installation.
This technique is both desirable and necessary as certain inputs cannot be added to the SPDS data base while at power operation.
For example, one cannot dismantle the neutron monitoring system while at power to modify switches and circuitry necessary to provide the inputs to SPDS.
Such work can only be done during an outage of sufficient duration; hence, full SPDS operation is scheduled after the anticipated completion date of the first refueling outage.
Schedule for incremental implementation of SPDS, following fuel load, is included in Attachment G.
It must be understood that LILCO fully intends to schedule work so that final completion of 3PDS is possible upon return from the first refueling outage.
However, should currently unforeseeable conditions surface to delay the implementation of some inputs by the completion of the first refueling outage, LILCO is committed to provide an SPDS that is in a state of "near completion" such that it could be declared operational without these remaining inputs.
The information requested on page 44 of the NRC " Agenda Package" given to participants at the regional workshop on February 22, 1983 requested two dates and a decision pertaining to NRC review.
As shown in Attachment F, a Safety Analysis is scheduled to be completed by January 1984, and the SPDS is scheduled to be declared operational by June 1986 (end of curre7tly planned first refueling outage) and declared complete no later than December 1986.
A pre-implementation review by the NRC is not requested.
/
ATTACHMENT A _ Page three When.Shoreham's-SPDS is completed, it will, as a minimum, be in accordance with the requirements of Section 4.1 of. Supplement 1 to NUREG-0737.
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G ATTACHMENT B' Detailed Control Room Design Review (DCRDR)
A preliminary human factors control room review was performed on the Shoreham Control Room'following the guidance given in NUREG/CR-1850 in March 1981.
This review complies with the requirements of NUREG-0700,. Chapter 6.
Since the 1580/ Chapter 6 review, the Human Engineering Discrepancies (HED's) generated therein have.been under resolution by LILCO and the NRC Human Factors Branch.
Many of
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the HED's identified in that review and in a similar review donducted at the site by the NRC are pending resolution on the
' basis of:whether or not they are included in-the emergency-event based review required by NUREG-0737, Supplement 1.
In accordance with par. 5.1 of NUREG-0737, Supplement 1, a
" dynamic" or event based analysis will be conducted using a task analysis (both workstation and cognitive analysis) based upon the Shoreham specific EOP's, discussed in Attachment-D, " Upgrade Emergency Operating Procedures".
Shoreham vill conduct this final portion of the DCRDR in l;
accordance with the general outline found in NUREG/CR-1270,- par.
3.6.1:
o Identification of all system functions (completed by BWR Owners' Group (BUROG))
.o Allocation of those functions to man or machine (completed by BWROG) o Definition of operator tasks (completed by B%ROG) f o
Task analysis in terms of information requirements, decision requirements and action requirements f
o (Task) analysis (in terms) of workstation and manning requirements
'o Preliminary (re) design o
Design evaluation using as-found control room
,o Review and revision of design using evaluation data o
Final design Test and' evaluation o
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ATTACHMENT B - Page two There are certain DCRDR activities which will require access to the control room and/or its operators.
Since Shoreham is zul NTOL plant and, fut order to minimize distraction to the operators during the critical power ascension phase, LILCO has decided to defer activities requiring operator and control room interface until after power ascension testing is completed.
This approach will enable some " operating experience" to be developed with the
- specifics of the Shoreham Control Room while at power operation.
A draft program plan similar in scope to that-suggested by NUREG-0700 will be submitted to the NRC by July 15, 1983.
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' ATTACH 11ENT C REGULATQRY CUIDE 1.97 - APPLICATION TO EMERCEllCY RESPONSE FACILITIES This Attachment presents information regarding the Shoreham status for the BWR variables listed in Regulatory Guide 1.97, Rev. 2 (RC 1.97). This Attachment includes:
- Table I, which lists the RC 1.97 BWR variables and their Shoreham status;
- Table II, which lists individual Shoreham valve position indicators, an expansion of the B-10 and D-24 entries on Table I;
- Table III, which lists various sensors and associated circuit components for Table 1 items, as applicable;
- Legend for the codes used on Tables I and II;
- Notes referenced on Tables I and II.
Tables I and II indicate whether the variable sensors, if located in a potentially harsh, accident-generated environment, have been determined to be environmentally qualified.
The notations used to give compliance status are taken from the Environmental Qualflication Report (Revision 4 was submitted via SNRC-768 dated Hovember 3, 1982) and apply to the sensors. The definition of the notations is also provided in the Legend in this Attachment.
The Shoreham commitment regarding environmental and seismic qualification for RC 1.97 B%R variables is as follows. %here LILCO has not taken specific exception in Tables I or II to the implementation of a RC 1.97 0%R variable or its qualifica-tion criteria, it is LILCO's intent to achieve seismic qualification of necessary channel components and environmental qualification of those sensors which are located in potentially harsh accident-generated environments. This qualification, in conformance to RC 1.97 categories for qualification criteria, will be achieved
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by start-up after the first refueling outage, which is currently estima'ted to be June, 1986 The variables for which LILCO is taking exception to the RC 1.97 qualification criteria are the following item numbers in Table I: A-1; B-1,4,5 and 8; C-1,3,6,14 and 15; D-3,5,8,ll,12,13,14,15,16,17 and 18; and E-2,3,4,7,8,9,11,12,13 and 14.
The nature of the exceptions are as noted in the Table.
All the variables shown on Table I as being displayed in the Ilain Control Room (liCR) will also be displayed in the Technical Support Center (TSC) and Emergency Opera-tions Facility (EOF) upon full implementation of the Safety Parameters Display System (SPDS), as discussed in Attachment A.
,=.. _
5 Indicating W/ neb 1.9)
Tchts 1 Itc2 Indicating SNPS-1 Cavice Envir, qual; LILC0 QA - Srnsor Powe r '
No.
V ritbis Devics Rcngs locati:n Guid211nso Catsgory location Supply _ Sche 41ula j
A-1 Coolant Fuel Zone
-308 to -108 (RGI)
I R5a73' RPSBUS Installed 4
Level in 1821-LR007 inches MCR RR (H21-P09)
A&C Reactor (B21-R615)
(H11-P601)
(P10)
Await generic resolution of 1821-LIOO7
(H21-P09)
RPSBUS ICC Detection issue prior to (821-R610)
(H11-P601)
(P10)
A&C taking any further actions.
Wide Range:
-150/0/60 (RG1) FT/IJ Refer to the settlement 4
i 1821-XR004A.B inches MCR I
RBS78' RPSBUS - of Shoreham OL hearing coa-(821-R623A B)
(H11-P601)
A&C tention SC3/ SOC 8 for further information on thc issue.
A-2 Reac tor IB21-XR004A,5 0 to 1,500 McR (RGI) RR I
RBS78':
IE Installed Coolant (821-R623A,5)
Feig (H11-P601) hl21-PO4)
System
.P05)
Pressure 4
A-3 Drywo11 IZ 93*PR501A,5
RBS78' IE Installed Pressure Psig (H11-PCM)
A-4 Sump Level (G11*LTS645A,5 0 to 37 in.
MCR (RGI) IA/IJ I
RBS8' IE Installed in Spaces (AC1/AC2) of Equipment Required for Safety j
1 A-5 Buypreeston 1Z93*LR001AlB
-90 in./0/+60 MCA (RGI) MR I
RBS8' IE Installed. High range indi-Pool ildide in.
(H11-PCrt) cator calibrated, }oe tange indicaior not 9et es11brated.
Level A-6 Drywell and IT48*02R125A,8 0 to 10%/
RBS112' IE Installed Suppression 0 to 30%
(ACH) i Chambef 0xygen Con-centration A-7 Suppression IZ93*TRS500A,8 50 to 250P MCR (RG1) EQ I
Supp Poni RPSBUS Installed 1 feat (H11-PCM)
A&B (6'iilow Morudi Pod! "vter Temperatuid M
Water Level) e s
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s
....s.
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.I Cumpliance Indicating W/ REC 1.97 Tr4blo 1 Indicatiyg SNPS-1 Devico F.nvir. Qu21. LILCO QA Sensor Power i
No.
Variable Device Ra ng-2 locctiIn Cuid: lines C*trgory Locatirs Supply Schedul2 itaa i
i B-1 Neutre1 Flux IC51*Xa802 10 to10 MCR
.N/A I
Incore Non-IE Installed equipment is sat-
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infactory for the interim (C51-R602)[SRM] Cis (H11-P603)'
MCR N/A I
Incore Non-IE period. System modifications will be completed by no (C51-R600A,B, (H11-P603)
- ;i MCR (RGI)
I Incore Non-IE later than the time of f
,g C,D)[IRM)
IC51*R803A,B, turn to power af ter thd
' f j (H11-P603) second refueling outage as-C.D I
suming timely generic
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f (C51-R603A,B, 7
C.D)[APRM]
resolution of this issue.
See Note A - Issue 2. and
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Note N.
B-2 control Rod No unique Full in or MCR (RG3)
II RBP-85' Non-IE Installed i
(CRD Position Mark Number not Full in (H11-P603)
Mechanism)
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B-3 RCS Soluble 1Z96-2025 100 to 1.100 (RG3)
PPM PASF W/A II PASF-40' Non-IE Installed Baron Con-
{
centration t
(Sample)
RBS78
RR I
(H21-P09)
RPSBUS See concent uvider B-4 Coolmat Fuel Zor.e
-308 to -108 (RCL) i Level in IB21-LR007 inches MCR (P10)
A&C Item No. A-1 (H11-P601)
Reactor (C21-R615)
R7 I
(H21-P09)
RP9 BUS NCR (F10)
A&C IB21-LI0d1 (H11-P401) g i
(821-R610)
Wide Range:
-150/0/60 (RG1)
I 1821-XR004A.B inches MCR FT/IJ RPS78' RPSBUS A&C (521-R623A,5)
(H11-P601)
N/A N/A N/A N/A N/A on hdid by NRC la accordance with N1t Prov d2d t
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B-5 BWR Core Supplement I to Therno-on Shorehas NUREG-0737.
couples B-6 RCS fiU llfM 1821-X LCD M.B 0-1,500 Psig MCR (RC1) RR I
RBS78's IE Installed
- i i
.t (H21-P04)
(Hil-P601)
(P05) e k
(821:523N 3)
S-7 Drywell IZ 93* PR501 A,5
RBS78' IE Installed
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6
C1mplieneo
"#18 indicating W/ REG 1.97 atsa Indicatirg SNPS-1 Device Envir. Qual.
LIII0 QA Seisor Powr No.
V:ri:bl2 Device Raige loc: tion-Cuid211ne2 Catraory locttion. Supply Schacute I
{.
A-S Drya ll Sump 1011-LR5051 0 to 48 in.
MCR N/A II C11-TK57 Non-IE Installed equipment Level (H11-P602) is permanently acceptable as is.
3 See Note A -
M e
.l h 4
Issue 4 1
'S B-9 Primary IZ 93*PR501A,5
RBS78' IE Installed Containment Psig (H11-PCN) f.
f Is r
Pressure 7.
ii7 !
B-10 Primary Various-N/A MCR (RG1)
(Note F)
Note F Note D Installed Containment (See Note F)
(Note F) i
,5 Isolation l
2 V'.1ve Position
{
(exc luding
.j i
4 Chec k. Valve)
N/A N/A h/A N/A N/A This parameter will not be C-1 Radioactiv-Not Provided ity Concen-on Shoreham implemented; alternate in-strumentation is available.
tration or See Note A - Issue 5 Raatation I
level in Circulating l
Primary Coolant I.,
C-2 Analysis of (Canberri-PASF 40' (RC3)
II PASF 40' Non-IE To B4 lastalled
,j Primary Multi-Channel h/A prior to fuel load 7
Coolant Analyzer)
(Camma 4
Spec trum)
N/A N/A N/A N/A N/A On hold,by NRC id 5ccor-i.
C-3 BWR Core Not Provided M i:e with Supplement 1 Thermo-on Shoreham to NUREC-0737 couples
?
C-4 RCS Presaire 1821-XR004A,5 0 to 1,500 MCR (RGI) RR I
RBS78':
IE Installed (521-R623A,5)
Peig (H11-P601)
(H21-PO4)
(P05)
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Compliancs Table.1.
9-Indict. ting. W/ REC 1.97 t
Ites I:dicatiIg SNPS-1 Devics Envir. Qus1. LIl40 QA Setsor
. Power No.
V;rir.blo Devica Rang 3 locction Guid311ne3 Catigory Loc; tion Supply Scheduls MCR (RC1) TA/IJ I
RBP78' IE Installed C-5 Primary ID21*RE085A,5 1 g/HR to containment 10 R/HR Area h'
Radiation j
C-6 Drywell IC11-LR5051 0-48 inches MCR N/A II C11-TK57 Non-IE See coma ats under Ites Drain Sumps (H11-P602)
No. B-8.
i Level (Iden-tified and Unidentiftel Leakage)
C-7 Suppression IZ 93*LR001A,3
-90 in./0/
RBS8' IE
~ Installed. High range indicator calibrated. Iow I
Pool Water
+60 in.
(H11-NM)
Level range indicator not yet calibrated.
9 C-8 Drywell IZ 93*PR501 A,5
,I RBS78' IE Installed Pressure Paig
'(H11-PCM)
C-9 RCS Pressure 1821-XR004A,5 0 to 1500 MCR (RC1) RR I
RBS78's IE Installed Paig (H11-P601)
(H21-PO4)
(P05) t C-10 Primary IZ 93* PR501A,8
RsS78' IE Insta)1ed i
p Containment Paig (H11-PCM)
Pressure C-11 containment IT48*H R114A,B 0 to 10%/
RSS112' It Installed 2
and Drywell 0 to 30%
(ACH)
Hydrogen Concentration C-12 contalftment IT48*0 R125A,8 0 to 10%/
RBS112'
.IE Installed 2
and Drywell O to 301 (ACH)
[
Oxygen Con-
}
centration (for inerted Containment
}
Plant) l i'
'4 Compliince Table"l i'
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11dicating W/ REC 1.97 Itao Indicating SNPS-1 Devics Envir.!Qu21.
LIIEO (K Sensor Power No.
Vcrisb13 Devica Rangi tocctisa Cuidilines Catsgory lacstim Supply. Schedule-t C-13 Containment ID11*RE021A 10~
/cc to ER (RC3) N/A I
HV63' IE* '
. Installed i
Effluent Ra 1D11*RE022A' 10~
Ci/cc ER (RC3) N/A I
HV63' IE*
- Power to heat tracing.
is non-IE
?
dioactivity
~
Noble Cases IDilePNL134 10 qCi/cc to ' ER (RC2) Mild I
TS113' IE j
(From Iden-10 q Ci/cc l,
tified Re-l_
g.
lease Points Including Standby Cas Treatment
)
i System Vent)
N/A N/A N/A N/A N/A This parameter will not be k
C-14 Radiation Not Provided implemented; alternate in-Exposure on Shoreham i
'strumentation is available.
Rate (Inside See Note A - Issue 6.
Building or
+
Areas, EC.
Auxiliary
- Building, Fuel Itan-diing, Build-ing, Con-tainment.
Which are'in Direct Con-tact with g
Primary Con-g tainment Where ?ene-trations and Hatches MP tocated)
'l C-15 Effluent ID11*PNL134 10'A.Ci/cc
' EK (RC2) Mild I
tilll3' 1E Installed Radiosctiv-ID11*PNL126 10j(Ci/cc
'ER (RC2) Mild I
T863' 15 See Note B ity-Koble Geses (from ID11*RE021A, 1x10~
1/cc ER (RG2) Mild I
HV63' IE*
- Power to heat tracing Buildings ao ID11eRP022A to 10~
1/cc ER (RC2) Mild I
HV63' 154 is non~1P.
-6 1
ID11-RE042 1x10 y t/cc ER (RC2) MA II RSS175' Non-1E to10]C1/cc e
2 v-
..e
~.
Touls a InJ1csting W/Rt.G 1.97 item Indicating SNPS-1 Device Envir. 4:c1.. LITE 0 QA Sensor Power.
ha.
Variab12
,Devico Rargi hection
.Cuidelines Ca t: gory.Iacitisa Supply Schedu13 i
6 D-1 P.ain Feed-IC32-FR020 0-12x10 LBS/ MCR (RC3)
II TB-37' Non-1E Installed -
water Flow (C32-R607)
HR (811-P603)
N/A i
f 5
~ $.
5 D-2 Condensate IP11-LI002 1 to 50 feet (RC3) N/A II Local Non-1E Installed 7?,
Storage Tank
-T.
Level D-3 Suppression Not Provided N/A N/A N/A
'N/A N/A This paraaoter will not be in-5 Chamber on Shoreham pienented.
Spray Flow alternato instru-mentation is avail-
't able. See Note A -
Issue 7.
II
- R8576, Non-1E Installed s
D-4 Drywell 1Z93-PI140
+
t.;
Pressure IZ 93-PR501A,5 Psia (H11-P601)
(RG2) EQ
.I R8878' 1E l '.
MCR i
]
(H11-PCM)
N/A N/A N/A N/A N/A Not Appli-D-5 Suppression Not Applicable Cable to Pont Water to Shoreham Shoreham l
Level (Weiit) 4 D-6 Suppression IZ 93*TRS500A,8 50 to 250F MCR (RC2) EQ I
Supp Pool IE Insta11' d I
e Pool Water (1 Foot Selow (H11-PCM) k 4
Temperature NWI.)
-II RBS Vari-Non-1E Installed D-7 Dryvell Compiter Points 40 to 440F MCR (RC2) EQ Atmosphere AS405 Thru (Main Pro-ous elev.
Temperattrre A8415 cess computer 1.*
CRT)
N/A N/A N/A N/A N/A See comments D-8 Drywell Not Provided RBS 63'2 under Ites No. B.8.
Spray Flow on Shoreham
[
D-9 Mdie steam-1E32-PIO31A,B, 0-25 Psig MCR*
(RC2) FT/IJ I
(H21-P74)
IE Installed g1-P654)
. ~~
line Isola-Ct D-0-100 Fils
, iUh4 r""*3 *T/I?
t (H21-P/4) ' IE tion Valves IE32-PIO32A,1, Leakage Con-C.D troi System 1E32-PIO33 0-100 Paig (H11-P655) (RG2) FT/IJ I
(H21-P73) ' 1E Pressure IE32-PIO34 0-25 Psig (H11-P655) (RC2) FT/IJ I
(H2'-P73) 1E IE32-PIO34 0-100" H 0 (H11-P655) (RC2) FT/IJ I
(H21-P/3)
LE f
1E32-FDIQ38 O-100" L 0 (H11-P654) (RC2) FT/IJ I
(H21-P74) 1E e
1 1
Coay11ance Tabic 1 l'
Indict.tLIg W/ REC 1.97 Item Indicating SNPS-1 Devics Envir. Qual. LIILO QA Stnsor Power No.
Vxtisbla Devics Range Locatite Cuideline)
Cat;giry locrtioA Supply Schedul) j t
d D-10 Primary Sys-IB21*PMU501 0 to 100 Psig MCR (RG2) EQ I
RBS 8' 1E Installed tem S.ifety (H11-P602)
(E21-P37) 3 Relief Valve RBS 40' d
Positions, In-(H21-P38) h}
ciuding ADS or
?.
Fiow Through Pressure in Valve Lines 6
N/A N/A N/A N/A N/A Not Appli-D-11 Isolation Not Applicable Condenser to Shorehas cable to Shorehae I
System Valve
'u Position N/A N/A N/A N/A N/A Not Appli-j.~,
D-12 Isolation Not Applicable W
Condenser cable to a
Shorehaa System Valve Position D-13 RCIC Flow IE51-FI003 0-500 CPN NCR (AG2) FT/IJ I
RBS 8' IE Installed (E51-R600-1)
(H11-P602)
(H21-F17)
See Note A-Issue 9 D-14 HPCI Flow IE41-FIO03 0-5,000 GPM MCR (RC2) FT/IJ I
RBS 8
AE Installed (H11-P601)
(H21-P14)
See Note A-Issue 9
?
D-15 Core 5 pray 1E21-F1002A,8 MCR (RG2) FT/IJ I
System flow (E21-R601A,B)
(H11-P601)
(H21-P01)
See Note A-Issue 9 i.
i D-16 LPCI System 1E11*FR001 0 to 20,000 MCA (M 3) Ff/*J t
llus d' It see Note A-Flow (E11-R608)
CPM (Hil-P601)
(H21-P18)
Issue 9 (P21) i D-17 SIIS Flow Not Provided N/A N/A N/A N/A N/A This parameter
,7 I
on Shorehaa vill not be imple-1 * {-
mented; altsrnate instrumentation is d
available. See Note A - Issue 9.
i f
i 4
Complirnes Tcble I j
Indicating W/ REG 1.97-Item IrdicatiYg SNPS-1 Devics Envir. Quel. LI143 QA Sersor.
Power No.
V2riable Devica Rarge locstion Guid31ines Catrgory loccti:2 Supply Schedule D-18 SICS Storage IC41-LT001 0 to 5,000 MCR N/A II RBS 113' Non-1E Installed equipment (C41-R601)
(H11-P603)
(H21-P11) is permanently acceptable as is.
See Note A - Issue 10.
R8S 8' j
D-19 RHR System 1E11*FR001 0 to 20,000 MCR (RC2) FT/IJ I
(H21-P18) 1E Installed Flow (E11-R608)
CPN (H11-P601)
(P21)
D-20 Rl'R Heat IE41-TR100 40 to 400F MCR (RC2) SQ I
RBS40' lNon-1E Installed y
Exchanger (E41-R605)
(H11-P614) a Oittlet Temperature
.D-21 Cooling IE41-TR100 40 to 320F MCR (RC2) EQ 1
RBS8' Non-1E Installed Wa t e r Tem-(E41-R605)
(H11-P614) perature to ESF System 7
Components
?
D-22 Cooling IE11*FIOO6A,5 0 to 12,000 MCR (RC2) FT/IJ I
RBS8' IE Installed Water Flow (E11-R602A,5)
CPM (H11-P601) to ESF System Componettth I
Radwaste Bldg D-23 High-Level IC11-LIO26A,8 0 to 25,000 (10114ML (an1) N/A 11 ItW1P Non-1El Installed I
{
Radioactive Cal 047)
Liquid Tank IC11-L100$A,8 (IC11-PNL (RC3) N/A II RW17' Non-1E i
Level 047}
IC11-LIO27A,3 (IC11-PFL (RC3) N/A II RW17' Non-1E 047) j IC11-LI169A,8
{hti- @
(RC1) N/A 11 P*lf 18=a-lE 04th IC11-LI175A,B (IC11-PNL (RG3) N/A II RW17' Non-1E 047)
(RC2) rote C' I
}*
D-24 Emergency t'dtious -
Open-Closed (MCRV,bd) -
bampers Ventilation (See Note G)
Damper-Position i
l 1
5 h
1
Compttance Table I g
Icdic2 ting W/ REG.I.97 Ites Indicati;g SNPS-1
.Devics Envir. Qu 1.
LIlf0 QA Sexsor Power No.
Virir.bla Device Range.
Ioc tion Guidelines Cat! gory locatim Supply Schedule i
D-25 Status of Emergency Voltages and Note E (RG2) Note H I
Note E 1E Installed Standby Buses Currents i
Power and IP50-PI116A.B 0 to 150 Paig MCR (RG2) MR I
RBS151' 1E Other Energy (NIP)
Sources Impertant to Safety (Hydraulic.
Pneumatic)
I
~E-1 Primary ID21*RE085A.B 1 to 10 R/HR MCR
_ RG1) TA/IJ I..
RSP 78' 1E Installed
(
Containment Area Radia-tion High Ranges N/A N/A N/A N/A N/A This parameter E-2 Reactor Not Provided kilding or on Shoreham will not be im-Secondary plemented; alterfate Containment instrumentation is Area Radiation available. See Note A - Issue 12.
a E-3 Radiation Not Provided N/A N/A N/A N/A N/A See Note A - Issue 13
[.
Exposure on Shorehas Rates (In-side k ilde I
ings or Areas Where Access 3
is Required to Service Equip-ment Important to Safety) m e
4
.6
Complirnce
.f _
.TGblo 1 Indictting W/ REC 1.97 l
Item Irdicatirg SNPS-1 Devics Envir. Qus1. LILCO QA Sensor Power No.
Vxri bis Device Ratge Location Guideline 3 Catag:ry Locittso Supply' Schedu13 i.
{.
E-4 Nable Cases Not' Applicable N/A N/A N/A N/A N/A Separate radiation monitor and Vent to Shorehas not needed since effluent Flow Rate:
discharges through common h.
Drywell plant vent.
J
}
- Purge, Standby Cas S
Treatment System Purge
,3 (for Mark I and II
{
Plants) f E-5 Noble Cases ID11*PNL-134 10 8 Ci/cc MCR (RG2) Mild I
T8113' IE*
Installed I
and' Vent togo 1/cc
- Power to heat
~
MCR (RG2) Mild I
HV63' 1E*.
tracing is non-1E.
Flow Rate: * '1D11*PNL-021, 10 10'I(to,4 Ci/ccMCR (RG2) Mild I
HV63' 1E*
Drywell
-022 Purge.
Standby Cas Treatment System Purge (tor Marks I, II and III Plan's)
E-6 Noble Cases Refer to E-5 See E-5 See E-5 See E-5 See E-5 See E-5 Installed and Vent
?
Flow Ratel f
Secondary Containment (Reactor Shield Building Annulus, if 4
in DealgM)
.~
G 3
6:..mp l ia nc e
- Table 1 Indicating U/ REC 1.97 i te:a Indicatirg SNPS-1 Devics Envir. Qunl. LIII0 (A Sensor Power' No.
Variabla Device Razg2 14ceti:o cuidelines
.Catrgtry locrti*s ~
Supply Schsdu13 E-7 Noble Cases Not Applicable N/A N/A N/A N/A N/A Separate radiation monitor and Vent to Shoreham not needed since af fluent Flow Rate discharges through common l
Auxiliary plant vent.
- ?
Butiding (including any Building Containing Primary Cases E.C.
Waste Cas Decay Tank
?$
~
RBS175' l2 E-8 Nc ble Cases
-1D11-RE042 10-6to10'I(,C1/cc l
MCR (RC2) N/A II (D11-P41)
Non-1E Installed 8
and Vent ID11*PNL126 10" to 10 J[C1/cc MCR (RG2) Hild I
TB63' IE See Note C i
Flow' Rate:
1U41-FT08 Q Oto401,011 CFM RBS175' (RG2) Mild II TB134' Non-1E Comron Plant ID11*FT069J TB63' (RG2) Mild I
TB99' LE Vent or Mul-tipurpose Vent Dis-charging Any of Above Releases (If Drywell or SCTS Purge is included) k E-9 Noble Cases Not Ayrdsable N/A N/A N/A N/A N/A Sepetite radiation monitor and Vent to Shorehas not needed since offluent 1 '
Flow Rate:
discharges through coanon All Other plant vent..
Identified Release Pointe a
j-f.
.h -
- h a
t a-(
4
J Complignes.
I-Indicati1g W/ REG 1.97 Itzo IIdicatirg SNPS-1 Devics Envir. Qu21. LI140 QA Seasor Power
,{'
No.
V riabl2' Device Rang 2 Loc: tion Cuidsliner Catrgory loc 2 tits' Supply-Scheduls E-10 Particulates 1T46*FRC004A,5 0-2.000 CFM MCR(H11-PVC2) (RC3) N/A I
RBS151' IE Installed i
and Halo ID11*FT069 0-401,011 CFM TB63' (RG3) N/A I
TB99' IE gens: All 1U41-FT035 0-4g,011,gFM RBS175' (RC3) N/A II T8134' Non-1E 1
identified 1D11-RE041 10 to10 NCR (RC3) N/A II RBS175' -
Non-1E Plant
/(Ci/cc j
Release Points. Sam pling with Onsite t
Analysis Capability E-11 Radiation Not Provided N/A N/A
.N/A N/A N/A On Hold Sased On Exposure on Shoreham July 1981 Meters Errata to (Continuous Reg. Cuide i
Indication 1.97, Rev. 2 at Fixed 1*
Incations)
N/A N/A N/A N/A N/A Portable equipment with i
E-12 Airborne Mark Numbers l'
Radio-Halo-not Applicable specified range I
gens and to Portable procured.
Par t icu la te's Equipment (Portable 2
Sampling D-with Onsite t
Analysis j-Capability)
E-13 Piartl had Mark Numbers N/A N/A N/A N/A N/A Portable equiparat with Environs not EppliEchle epsdified tenge Radiation to Portable precated.
(Portable Equipment l
Instrumen-
.l l,
tation) t w
8 h
i
'4
Compliance, Indicating W/ REC 1.97 Item Indicating SNPS-1 Devica Envir. Quel.. Lilf0 QA Sensor
. Power No.
Varichts Devica Rang 1 locati;A Cuidalinea Cattgory loceti:n Supply Schedu13 l
E-14 Plant and Mark Numbers N/A N/A N/A N/A N/A Portable equip-
[
Environs not Applicable ment with speci-e Radioac ti-to Portable fied range
'l vity (Por-Equipment procured.
table Ins-t rumen-tation)
E-15 Wind P64-IR501 0-540' MCR (RC3) N/A II
. Meteor.
Non-1E Permanent Instal-
,j Direction (P64-EMP)
Tower lation underway.
~
{
E-16 Wind Speed P64-XR503 0 to 45 MPS MCR (RC3) N/A II Meteor.
Non-1E Perranent instal-(0 to 100 (P64-EMP)
Tower lation underway.
MPH) 1 E-17 Estimation P64-IR502
-10 to 20F MCR (RC3) N/A II Meteor.
Non-1E Permanent instal-i of Atmosphe-(33 and 50 ft. (P64-EMP)
Tower lation underway.
ric Stabi-Interval) lity l
E-18 A.:ctdent Non-1E Installed (RC3) N/A Sampling Capability I,
Primary Coolant and 1-k Susp:
i~
4 4
j
-Grose 1896-RM-011, 8 Decades IZ96-PNL-(RC3) N/A II PASF -40' Non-1E Installed i
j Activity 012. 013 0.1p/hrto PASF j
1x10 mR/hr
.' j 4
To be i
(RG3) N/A II
-Camma See C-2 i
Spectrum Installed i
Prior to j
Fuel Load
}
t l
-Boron 1Z 95*5025 100 to 1,100 PASF
.(RC3) N/A II PASP -40' Non-1E Installed-
{
~
Content FiM g
'[
1 i
I g'
f.
Compliance Table 1 W/ REG 1.97-Indicating Item Izdicatirg
.SNPS-1 Devics Envir. Qual. LILCO QA Sensor Power i
No.
Vrrichls
- Devica Rang 2 locatias Cuid311nes Cat: gory loc tica Supply Schedu13 E-18 (Cont'd)
-Chloride IZ 96-C1Z O14 0.1 to 100 PPM PASF (RG3) N/A II PASF-40' Non-1E' See Note M Content
}
IZ 96-E 152 0 to 20 PPM PASF (RC3) N/A II PASF-40' Non-1E Installed
-Dissolved By Analytical 0 to 2,000 PASF (RC3) N/A II PASF-40' Non-1E Installed Hydrogen Calculation ec(STP)
Total Cas Kg II PASF-40' Non-1E Installed
.-Dissolved IZ96-021-147 0 to 19.99 PASF 0xygen PPM II PASF-40' Non-1E Installed
-pH IZ 96-E-025 1 to 13 PASF i
Non-1E. Installed (RC3) N/A E-19 Accident Sampling Capability Containment Air:
l I
RBS112' IE Installed
-Hydro 6en
- IT48*H R114A,5 0 to 101/
MCR Content 0 to 30%
(ACH) f 2
-Oxygen IT48*0 R125A,B 0 to 10%/
MCR I
RBS112' 1E Installed I:
'h 2
Content 0 to 30%
(ACH)
Non-1E To be
-Camme See C-2 Installed i
Spectrum Prior to Fuel lead i
I i
.e j
5 i
-.g i
~
TABLE II ITEM D24:
EMERGENCY VENT DAMPER POSITION
- Compliance w/ REG 1.97 LILCO Location.of Limit Switch Indicator Envir. Qual.
QA Limit Switch Power Mark No.
Location Guidelines Category
& Valve Supply IT46*PNS034A,B VC2 RR I
RBS-182' IE IT46*PNS035A,B VC2 EQ I
RBS-112' IE IT46*PNS037A,B VC2 EQ I
RBS-95' IE i,
i f
- For schedule status, see Item D24 on Table I.
'l Note:
All indicators are located in the main control room (MCR).
i i
h I
i j
~,-
TABLE II (continued)
ITEM BIO:
CONTAIN ISOL VALVE POS INDICATION **
Compliance K
w/ REG 1.97 LILCO Location of i
Limit Switch Indicator Envir. Qual.
QA Limit Switch Power Mark No.
Location Guidelines Category
& Valve Supply (Note L)
IB21*MOV062 H11P601 EQ I
RBS-78' IE IB21*MOV063 IlllP601 EQ I
RBS-78' 1E IB21*MOV064 IlllP601 EQ I
RBS-78' IE IB21*PNS036A,B H11P602 RR I
ST-87' IE IB21*PNS081A-D H11P602
'RR I
RBP-82' IE IB21*PNS082A-D H11P601 RR I
ST-82' lE IB21*SOV313A,B AC1 EQ I
RBS-78' IE IB31*PNS081 H11P602 RR I
RBD-133' IE IB31*PNS082 H11P601 RR I
RBS-155' IE IC41*EV010A,B H11P603 N/A (Note J)
I N/A (Note J) 1E IC51*SOV028 MXP EQ I
RBS-78' IE IC51*EV801A-D H11P601 (Note K)
N/A (Note K)
I N/A (Note K)
Non-lE IDll*MOV032A,B MXP EQ I
RBD-101'/
lE RBS-63' 1D11*MOV033A,B MXP EQ I
RBD-101'/
1E RBS-63' IE11*PNS031A-D H11P601 EQ I
RBS-24' lE lEll*PNS037A,B H11P601 EQ I
RBS-72' IE 1E11*MOV038A,B H11P601 EQ I
RBS-103' 1E lE11*MOV039A,B H11P601 EQ I
RBS-103
IE 1E11*PNS040A,B lil l P601 EQ I
RBS-72'.
IE 1E11*MOV041A,B H11P601 EQ I
RBS-51'/40' 1E 1E11*MOV042A,B II11 P 601 EQ I
RBS-29' IE 1E11*MOV044A,B I!11P601 EQ I
RBS-17' lE 1E11*MOV045A,B H11P601 EQ I
RBS-17' lE 1E11*PNS041 H11P602 EQ I
RBD-84' IE-lE11*PNSO48 1111 P601 EQ I
RBS-63' lE 1E11*MOV053 IlllP601 EQ I
RBS-103' IE 1E11*MOV054 HilP602 EQ I
RBD-104' lE IE11*MOV055A,B H11P601 EQ I
RBS-45' IE 1E11*MOV056A,B HilP601 EQ I
RBS-45' IE lEll*MOV081A,B H11P601 EQ I
RBD-8.l' IE s
- For schedule status, see Item B10 on Table I.
l Note:
All indicators located in the main control room (MCR).
l
l TABLE II (continued)
ITEM B10**
Compliance w/ REG 1.97 LILCO Location of Limit Switch Indicator Envir. Qual.
QA Limit Switch Power Mark No.
Location Guidelines Category
& Valve Gupply lEll*PNS081A,B HilP601 RR I
RBP-79' IE lE21*MOV033A,B lil l P601 EQ I'
RBS-104' IE 1E?l*MOV034A B HilP601 EQ I
RBS-15' IE lE21*MOV031A,B HilP601 EQ I
RBS-24' IE lE21*MOV035A,B lillP601 EQ I
RBS-53' IE 1E21*MOV081A,B H11P601 EQ I
RBD-128'
~
lE lE21*PNS081A,B HilP601 RR I
RBP-126' IE lE41*MOV032 H11P601 EQ I
RBS-24' IE 1E41*MOV036 H11P601 EQ I
RBS-20' IE 1E41*MOV041 H11P601 EQ I
RBD-66' IE lE41*MOV042 H11P601 EQ I
RBS-63' IE 1E41*MOV044 HilP601 EQ I
RBS-30' IE lE41*MOV047 HilP601 EQ I
RBD-66' IE 1E41*MOV048 H11P601 EQ I
RBS-64' 1E
'4 1E41*MOV049 HilP601 EQ I
RBS-34' IE 1E51*Mov032 H11P602 EQ I
RBS-24' IE lE51*MOV036 H11P602 EQ I
RBS-18'
-lE lE51*MOV041 HilP602 EQ I
RBD-88' IE' IE51*MOV042 HilP602 EQ
'I RBD-88' IE lE51*MOV047 H11P602 EQ I
RBD-88' lE 1B21*MOV031 H11P602 EQ I
RBD-79' 1E IB21*MOV032 H11P601 EQ I
RBS-79' IE IB21*MOV061 HilP601 EQ I
RBS-78' IE 1E51*MOV048 HI1P602 EQ I
RBS-88' IE 1E51*MOV049 111 I P 602 EQ I
RBS-34' 1E lE51*MOV045 HilP602 EQ I
RBS-31' IE lE51*MOV046 HilP602 EQ I
RBS-29' IE IG11*MOV246 HilP602 EQ I
RBS-40' IE IC11*MOV247 HilP601 EQ I
RBS-40' IE 1G11*MOV248 H11P602 EQ I
RBS-40' IE IG11*MOV249 HllP601 EQ I
RBS-40' IE 1G11*MOV639C PCM EQ I
RBS-20' IE 1G33*MOV033 HilP602 EQ I
RBD-121' LE
~
- For schedule status, see Item B10 on Table I.
Note:
All indicators located in the main control room (MCR).
-TABLE II (continued)
ITEM B10**
Compliance w/ REC 1.97 LILCO Location of
-8
~
Limit Switch Indicator Envir. Qual.
QA Limit Switch Power Mark No.
Location Guidelines Category
& Valve Supply IG33*MOV034 HilP601 EQ I
KBS-121' IE IG41*MOV033A,B MXP EQ I
RBS-46' IE
}
IG41*MOV034A,B MXP EQ-I RBS-30' IE
{
lP42*MOV035 MXP EQ I
RBS-67' lE l
IP42*MOV036 MXP EQ I
RBS-67' IE IP42*MOV047 MXP EO-
.I RBS-68' lE j
IP42*MOV048 MXP EQ I
RBS-68' IE.
IP42*MOV147 MXP EQ I
RBD-74' IE I
1P42*MOV148 MXP EQ I
RBD-74' IE IP42*MOV231 MXP EQ I
RBS-66' IE l
IP42*MOV232 MXP EQ I
RBS-67' IE IP42*MOV233 MXP EQ I
RBS-68' IE
^l
'IP42*MOV234 MXP EQ I
RBS-69' IE' e
IP42*MOV235 MXP EQ
.I RBS-70' IE l
IP42*MOV236 MXP EQ I
RBS-66' IE i
1P42*MOV237 MXP EQ I
RBS-67' 1E 1P42*MOV238 MXP EQ I
RBS-68' 1E l
IP42*MOV239 MXP EQ I
RBS-69' IE IP42*MOV240 MXP EQ I
RBS-70' IE j
IP50*MOV103A,B MXP EQ I
RBS-78' I E-1 IP50*MOV104 MXP EQ I
RBS-20' IE IP50*MOV106 MXP
.EQ I
RBS-20' IE IT23*MOV031A,B MXP EQ I
RBS-40' IE IT24*PNS001A,B ACH RR I
RBS-40' IE IT24*PNS004A,B ACH RR I
RBS-40' IE IT46*PNS038A-D VC2 EQ I
RBP-78' IE IT46*PNS039A-D VC2 EQ I
RBP-il2'/RBS-40' IE IT46*PNS078A,B ACH RR I
RBS-90'/96' IE g
IT46*PNS079A,B ACH EQ I
RBS-63' IE-i IT48*MOV031A,B ACH EQ I
RBS-67'/73' IE I
i
~
- For schedule status, see Item B10 on Table I.
Note:
All indicators located in the main control roon (MCR).
I t
TABLE II (continued)
ITEM B10**
Compliance w/ REG 1.97 LILCO Location of Limit Switch Indicator Envir. Qual.
QA Limit Switch Power Mark No.
Location Guidelines Category
& Valve Supply IT48*MOV032A,B ACH EQ I
RBD-71' IE IT48*MOV033A,B ACH EQ I
RBS-51' IE IT48*MOV034A,B ACH EQ I
RBS-51' IE IT48*MOV035A,B ACH EQ I
RBS-68'/73',
RBS-73'/72' IE IT48*MOV038A,B ACH EQ I
RBS-51' IE IT48*MOV040A,B ACH EQ I
RBS-51' IE 1T48*SOV126A,B AC1/AC2 EQ I
RBS-63' IE IT48*SOV127A,B AC1/AC2 EQ I
RBS-40' IE IT48*SOV128A,B AC1/AC2 EQ I
RBS-78' IE IT48*SOV129A B AC1/AC2 EQ I
RBS-40' IE IT48*SOV130 ACI EQ I
RBS-63'
RBS-63' IE lE32*MOV021A-D H11P654 EQ I
RBS-78'
RBS-8' IE lEll*SOV169 AC2 EQ I
RBS-8' IE IC51*S0V801A-D HilP601 (Note K)
IJ I
RBS-78' Non-IE
- For schedule status, see Item B10 on Table I.
Note:
All indicators located in the main control room (MCR).
4 Page 1 of 4 4
TABLE III Item No.
Sensors and Associated Ccmponents A-1 IB21* LIT 007A,8 1821*LT155A,C A-2 IB21*PT004A,B A-3 1Z93*PT003A,B 1R41*E/S506A,B A-4 1G11*LE645A,B 1Gil*LIS645A,B IC11*LAH 1R41*E/S506A,0 A-5 1Z93*LT001A,B 1Z93*LT012A,B 1R41*E/S506A,B A-6 IT48*02IT123A.B IT48*02Z123A,B IT48*02I123AX,AY IT48*02I123BX,0Y IT48-02AH IT48*02IT124A,B IT48*02Z124A,8 1T48*02I124AX,AY 1T48*02I124BX,8Y 1T48*PHLO68A,B 1T48*PNLO69A,0 A-7 1Z93*TE110-113W,X,Y,Z 1Z93* TIS 110W,X,Y,Z 1R41*E/S507W,X,Y,Z 1Z93-TAH 1
B-1 Various B-4 1821* LIT 007A,B 1021*LT155A,C B-6 1821*PT004A,B B-7 IZ93*PT003A,B 1R41*E/S506A,8
Page 2 of 4 TABLE III Item Ho.
Sensors'and Associated' Components B-8 1011-LT210 IC11-LR505 1R41*E/S509 B-9 1Z93*PT003A,8 1R41*E/S506A,B C-4 1821*PT004A,B C-6 1011-LT210 1G11-LR505 1R41*E/S509 C-7 1Z93*LT001A,8 1Z93*LT012A,B 1R41* E/S506A,B C-8 1Z93*PT003A,B 1R41*E/S506A,B C-9 1821*PT004A,B C-10
'lZ93*PT003A,B 1R41*E/S506A,B IT48*H Z115A,B C-11 2
IT48*H 1T115A,B 2
1T48*H 1115AX,0X 2
1T48H I115AY,BY 2
IT48*PHL6SA,0 H341 arms (High) 1T48*H Z116A,8 2
1T48*H IT116A,B i
2 1T48*H I116AX,0X 2
1T48*H I116AY,BY 2
1T48*PHLO69A,B C-12 See Item Ho. A-6 C-15 1D11*RTS021 1D11*RIS021A,B,C 1D11*PHLO21A,B l
ID11*RTS022 1D11*RIS022A,B,C 1D11*PULO22A,B 1011-RTS041 l
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Page 3 of 4 TABLE III Item No.
Sensors and Associated Components
, C-15 (Cont'd)-
1D11-RISO42 1011-pillo 41 1D11*RR106 1D11*RR107 1011-RR101 RAH's (Radiation Alarm High)
D-4
'lZ93*PT003A,B 1R41*E/S506A,B 1Z93-PT140 1Z93-PS140 Pressure Alarm High D-6 See Item tio. A-7 D-7 1T47-TE027A-L D-9 IE32*PT031A-D 1E32*PS031A-D 1E32*PT032A-D 1E32*PS032A-D 1E32*PT033 1E32*PS033 IE32*PT034 1E32*PS034 1E32*PDT035 1E32*PDS035 IE32-PAL 1E32*PDT038
-1E32*PDS038 IE32-SRU2,3,4,5 D-10 1821* PT153A-L 1821*PIS153A-L 1821-PAH D-13 1E51*FT00?
1E51*FE003 IE51*FS003 1E51*fIC003 1E51*FK003 1E51-FAL D-14 1E41*FT003 1E41*FE003 lE41*FS003 IE41*FK003 1E41dFIC003 1E41*FAL e-
I
/
Page 4 of 4
' TABLE III Item No.
Sensors and Associated' Components D-15 IE21*FT002A,B IE21*FE002A,B 1E21*FIS002A,B D-19 IE11*FT001A,B IE11*FE001A,B IE11*FI001A,B
'1E11*PDS001A,8 IE11*FK001A,B IEll-SRUIA,B D-20 1E11-TE012A,B D-21 1E11*TE013A,B D-22 IE11*FT006A,B IE11*FE006A,8 SRUlA SRU1B D-25 1P50*PT116A,8 1P50*PS116A,B PAH/L (Pressure Alarm High/ Low) 1R41*E/S60 E-1 ID21*RISOSSA,B 1D11*RR502 1D11*RR503 E-5 1D11*RTS021 1D11*RE021A,B ID11*RIS021A,B,C 1D11*RTS022 1D11*RE022A,B ID11*RIS022A,B,C 1D11*RP106 1D11*RR107 RAH's (Radiation Alarm High)
E-6 See Item No. E-5 E-8 1U41-FE0S5 ID11-RTS041 ID11-RR101 1Dll-RISO42 IDil-PNLO41 1Dll*PNLO69 1011-RAH
LEGEND FOR TABLES I A!!D II 0F ATTACHitENT C O
Key.to Symbols Used in Tables I and II, Attachment C to SilRC-863 NRC Regulatory Guide 1.97 Oualification Criteria (RGl) - Category 1 Environmental Qualification Criteria
-(RC2) - Category 2 Environmental Qualficiation Criteria (RC3) - Category 3 Environmental Qualification Criteria Environmental Qualification Status
.EQ
- Environmental Qualification Complete FT/I3 - Further Testing or Analysis Heeded; a 3astification for Interim Operation Pending Completion is Provided in the Environmental Qualification Report for Class IE Equipment - Shoreham Huclear Power Station MR
- Modification Recommended and Will be Implemented Prior to fuel Load, Thus, Completing Environmental Qualification RR
- Replacement Recommended and Will be Implemented Prior to Fuel Load, Thus Completing Environmental Qualification TA/I3 - Testing and/or Analysis Program Has Been Initiated; a Justification for Interim Operation Pending Completion is Provided in the Environ-mental Qualification Report for Class 1E Equipment - Shoreham Huclear Power Station Mild - Location of Sensor is !!ot in a Potentially Harsh, Accident-Cencrated Environment i
l N/A
- Hot Applicable Locations HV
- Heating and Ventilation Equipment Room liCR
- Main Control Room PASF - Post-Accident Sampling Facility RBD
- Reactor Building Drywell RBP
- Reactor Building Primary Containment
-.,-----av._,
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Locations (Cont'd.)
- Reactor Building Secondary Containment RW
- Radioactive. Waste Building ST
- Steam Tunnel TB
- Turbine Building l
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HOTES FOR TABLES I N!D II 0F ATTACH!!EtlT C Il0TE A - The BWR Owners' Group has investigated the recommendations of Regulatory Guide 1.97 Rev. 2 as they relate to the bur and has issued a report en-titled, "B%R Owners' Group Position on NRC Regulatory Guide 1.97 Rev.2" dated July 1982, to the utilities and the NRC.
This report was formally transmitted to the NRC on April 6, 1983.
There are a number of generic issues in which deviation from the Reg.
Cuide recommendation is proposed and justified. These issues are re-ferred to by number, as appropriate, throughout the table.
HOTE B - The low-range normal station vent monitor (lDll-RE042) channel will not be qualified seismically or for harsh environment. This equipment is covered under Reg. Cuide 1.97 note 9 whereby "(e)xisting equipment may be used to monitor any portion of the stated range within the equipment design rating."
HOTE C - The low-range normal station vent monitor (IDll-RE042 and 1U41-FT095) channel will not be qualified seismically or for harsh environment.
This equipment is covered under Reg. Cuide 1.97 note 9 cited above in Note B.
NOTE D - (Item B10): All power supplies are Class IE except for TIP Ball valves (C51*S0V801A-D) and shear valves (C51*EV601A-D).
NOTE E - (Item D25): All Class IE motor control centers are monitored for voltage by a relay in the secondary side of each Class 1E circuit.
In addition, the diesel generators are monitored for voltage and current output when in operation.
NOTE F - (Item B10): See Table Il for containment isolation valve position indication.
HOTE C - (Item D24): See Table II for emergency damper position indication.
NOTE H: See the latest revision to the Environmental Qualification Report for Class IE Equipment - Shoreham fluclear Power Station for the environ-mental qualification status of those Class 1E flCC's which are located in potentially harsh, accident-generated environments.
NOTE 3 - These explosive squib valves are normally closed (t!C); they explode to open; position indication consists of a local meter and indicator lights in the llain Control Room, Indicating continuity in explosive circuit and implying valves are still closed (safe position for containment isolation).
9 HOTE K - The TIP Ball (S0V801) and shear (EV801) valve position indication consists of an anndnciator window which shows either "all valves closed" or "any valves open." The Ball valve limit switches do not have separate mark numbers. The shear valve position is de-tected by continuity of its explosive circuit corresponding the normally open condition.
NOTE L - Where the limit switch is integral to the MOV/S0V, no separate limit switch mark number is shown; item is referenced to the MOV/SOV mark number.
'HOTE M - Chloride Analyzer from Orion Research is still under development and will be installed as a post-fuel load modification if the manufacturer can provide a working instrument. An ion chromatograph (XZ152) has been installed to measurs chlorides since the Orion equipment was not available.
-HOTE N - Parts of this loop will be replaced for signal compatibility with SPDS computer system.
2
-/.
ATTACllMENT'u Upgrade Emergency Operating Procedures I.
Current Status of Emergency Operating Procedures (EOP)
Shoreham Nuclear Power Station has already implemented emergency procedures based on the BWR Owners Group Emergency Procedure guidelines.
The following is a brief synopsis of the emergency procedure upgrade development to date.
In a letter dated October 21, 1980-from D. G. Eisenhut (NRC) to S. T.
Rogers, the NRC indicated that the generic emergency procedure guidelines prepared by General Electric and the BWR Owners Group were acceptable for trial implementation at Shoreham.
Based on this letter, LILCO developed procedures that are based on Revision 1B of the GE generic emergency procedure guidelines and submitted them to the NRC in July, 1981.
On September 16, 1981, LlLCO. met with the NRC staf f and Battelle Pacific Northwest Laboratories (Battelle) to discuss their comments on these procedures.
The general comments included human factors considerations on the use of standard logic format, interaction with non-emergency procedures, and the adequacy of the graphs that were included in the procedures.
On October 16, 1981, the emergency procedures were run for the NRC staff and Battelle on the Limerick Simulator.
The plant operators used the emergency operating procedures to respond to simulated transients which required the concurrent use of the procedures and which varied from transients of minor nature to transients involving multiple system failures.
On October 17, 1981, the LILCO Plant Staff l
walked through the emergency operating procedures for the
(
NRC staff and Battelle in the Control Room of Shoreham i
Nuclear Power Station.
The interaction between the operators, the procedures and the control panels was evaluated at that time.
l.
Additional comments were generated by the NRC staff and i
Battelle based on the simulator demonstration and the Control Room walk-through.
LILCO then revised the emergency procedure to incorporate the additional comments.
The procedures were also revised to include a two column format in accordance with l
NUREG-0799, the left hand column being used for action statements and the right hand column for notes and explanations.
The emergency procedures were then submitted i
to General Electric for review and cctment.
LILCO received i
).
ATTACllMENT-D - Page two comments from General Electric, dispositioned the comments and forwarded the comments and the disposition of the same to the NRC'on 1/22/83.
The Safety Evaluation Report dated February, 1983, NUREG 0420, Supplement No. 3, considered item I.c.8g of NUREG 0660 complete for issuance of an operating license.
II.
Procedure Generation Package.
In response to the integration requirements of NUREG 0737, Supplement 1, the EOPs will be subjected to a final validation as part of the plant specific event-based analysis associated with the DCRDR.
Furthermore, it is now anticipated that a. procedure. generation package will be submitted approximately 6 months prior to the first refueling outage.
This package will describe the method used to develop emergency operating procedures from the generic guidelines and also justify any deviations from the generic _ technical guidelines.
In addition, a plant specific writers guide which details specific human factors used in preparing emergency operating procedures, a description of the verification / validation program and a description of the training program will be provided.
The schedule for the submittal of the procedures generation package, as well as the updating of the EOPs, training and implementation to the m'ost current version of the EOPs, is depicted in Attachment F.
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-~__.a Attachment E Emergency Response Facilities This attachment provides information on the extent to which the Shoreham Technical Support Center (TSC), Operational Support Center (OSC), and Emergency Operations Facility (EOF) comply with the requirements of Generic Letter 82-33.
At Shoreham these facilities are scheduled to be operational at fuel load.
The paragraphs belot are numbered to be consistent with those of the generic letter.
Responses - 8.2 Technical Support Center (TSC) 8.2.1.a The TSC when activated is staffed by predesignated tech-nical, engineering, management and other licensee per-sonnel.
Dedicated office space has been provided for use by NRC personnel.
The TSC will be activated upon the declaration of Alert, Site Area or General Emergency.
The TSC will operate uninterrupted to provide plant management and technical support to plant operations personnel, and to relieve the reactor operators of peripheral duties and commu-nications not directly related to reactor system manipulations.
The TSC will perform all EOF functions until that facility is operational and a transfer of responsibility has taken place.
8.2.1.b The onsite Technical Support Center is located within the protected area in the Office and Service Building Annex and connected to the Office and Service Building by an overpass.
The TSC is within tw, minutes walking distance from the control room.
Due to its location and communication capabilities, the TSC is capable of providing the necessary interaction with the control room, OSC, EOF, and other emergency personnel.
8.2.1.c The TSC is a two story structure with a total floor area of approximately 9,000 square feet.
Adequate working space and conference facilities are available for a minimum of 45 people (25 on the second floor and 20 on the first floor).
In addition, a separate computer room is pro-vided for the ERF and SPDS computers as well as storage areas for TSC equipment, plant documents and historical data.
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8.2.1.d The TSC structure is designed as a Seismic-Category I structure.
Additionally, the TSC structure has been designed for winds associated with the design basis tornado and wave forces associated with the probabic maximum-hurricane.
8.2.1.e The TSC has been equipped with HVAC systems to control air temperature and humidity for personal comfort and equipment performance.
These systems maintain a positive pressure within the TSC to prevent infiltration of outside air during emergencies.
In addition, the TSC HVAC system is' capable of circulating both outside air and recirculating inside air through a special filter _ train containing charcoal during emergency operation.
- 8. 2.1. f - The TSC meets the_ radiological habitability criteria, as follows:
1.
Eighteen inches of concrete shielding is provided to protect TSC personnel from post accident radiation sources outside the TSC.
2.
The TSC atmosphere is filtered through a charcoal-HEPA filter.
A 99 percent efficiency _ credit is taken for filtration based upon adherence to the guidelines established in Table 2 of Regulatory Guide 1.52 follows:
3.
A portable, dedicated continuous airborne monitor, with an iodine cartridge and a particulate filter is provided within the TSC to monitor airborne activity levels.
This monitor includes variable setpoints with audible and visual alarms to alert personnel to increasing airborne activity.
This monitor is sensitive to radiciodine concentrations as low as 10-7.uci/cc.
In addition, two portable, dedicated
)
area monitors are provided within the TSC to provide continuous measuring of direct radiation levels.
These monitors also include variable setpoints with audible and visual alarms.
8.2.1.g The TSC is' equipped with reliable primary and backup communiciations systems consisting of hotlines, NAWAS dedicated lines commercial telephone, emergency card dialer telephone, private automatic exchange,
+
public address and party lines, sound powered telephones and two-way radio.
These communications systems are used for intraplant communications, communications with outside agencies and for communications to other ERF locations.
e 8.2.1,h Shoreham will use the current Phase I data system for fuel load and thereafter until the Phase II system (see Attachment A) becomes operational.
8.2.1.i The TSC will have on file accurate and up'to date plant documents essential for evaluation of the plant under accident conditions. _ For a listing, refer to letter
-SNRC-643 dated December 12,1981.
~
8.2.1.j
.The TSC is staffed with sufficient licensee designated' technical engineering and licensee management personnel to provide the necessary support to the control room.
during emergency conditions.
The activation of the.TSC is accomplished within 60 minutes of the declaration of an Alert, Site Area, or General Emergency.
Upon activation, the TSC succeeds the control room as the emergency response command post and functions in this capacity until'the EOF is appropriately staffed and activated.
8.2.1.k.The TSC design in itself is an example'of the use of-human factors engineering principals.
This is exemplified by its layout, adequate work areas, storage space and
-ease of movement throughout the facility.
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s 6-J Responses - 8.3 Operational Support Center (OSC) 8.3.1.a The Operational Support Center is located in the Office and Service Building, located north-northwest of the Reactor Building, adjacent to the Turbine Building.
An alternate OSC will be located in the basement of the TSC.
The OSC will provide a location where support personnel can assemble and where plant logistic support can be coordinated.
Both locations are within two minutes. walking distance of the TSC and~ control room.
The OSC coordinator will coordinate the arrival and dispatch of technicians and interface with the TSC on corrective action related matters.
8.3.1.b OSC support personnel will. report to the OSC when acti-vated at the Alert classification.
These personnel include:
Instrumentation & Control Technicians, Mechanics, Electricians, Radiation Protection Technicians, Inplant Radiation Monitoring Technicians, Onsite/Offsite Radia-tion Monitoring Personnel and Radio-chemistry Technicians.
The above personnel are capable of supporting those tasks and functions assigned by the OSC coordinator.
8.3.1.c The OSC is connected to both the TSC and control room by dedicated telephone.
In addition, commercial. telephone is-also available to facilitate onsite and offsite com-munications.
The OSC is also equipped with portable radio units which are tuned to the inplant radio frequen-cies.
These frequencies are also accessible in the TSC and control room, thus providing back up to the dedicated telephone lines.
e Response - 8.4. Emergency Operations Facility (EOF) 8.4.1.a' The EOF is a licensee controlled and' operated offsite support center.
The EOF has facilities for and.provides management of overall licensee emergency response, coordination of radiological and environmental assessment,
' determination of recommended public protective actions, and~ coordination of emergency response activities with Federal, State and local agencies..
When the EOF is activated, it shali be staffed by licensee, Federal, State, local and other. emergency personnel designated by the Emergency Plan to perform these functions.
A designated senior licensee official shall manage licensee activities in the EOF to support the designated official in the TSC and the senior reactor operator designated as the shift supervisor in the control room.
Facilities shall be provided in the EOF for the acquisition, display, and' evaluation of all radiological,'meteoro-logical ~, and plant system' data pertinent to determine offsite protection measures.
These facilities will.be used to evaluate the magnitude and effects of actual or potential radioactive releases from the plant and to determine offsite dose projections.
8.4.1.b The EOF is located approximately 19 miles from the-Shoreham. Nuclear Power Station.
No special radiation protection features or radiological monitoring equipment are required, in accordance with Table 1 of Supplement 1 to NbREG 0737.
The distance of 19 miles between the EOF and the Shoreham site assures EOF habitability and virtually precludes the possibility of significant airborne radioactivity con-centrations.
Field survey teams, operating from the EOF, will detect and track any airborne activity which could reach the EOF well before it would be picked up by an EOF airborne monitor.
8.4.1.c Sufficient facilities have been provided, in the EOF when activated, to accommodate and support Federal, State and licensee predesignated personnel, equipment and documentation in the EOF.
e j
8.4.1.d The EOF which serves as the LILCO Training Center under normal.(non-emergency) conditions has been built in accordance with the New York State Building Code.
8.4.1.c The EOF is sufficiently equipped to provide controlled humidity and temperature for personal ~ comfort and equipment performance.
8.4.1.f
.The EOF.is equipped with reliable primary and backup communications systems consisting of hotlines, dedicated lines, NAWAS commercial telephone, private automatic exchange and two-way radios to appropriate plant locations, outside agencies and other ERP locations.
S.4.1.g Shoreham will use the current Phase I data system for fuel load and thereafter until the Phase II system (see Attachment A) becomes operational.
8.4.1.h The EOF will have on file accurate and up to date plant documents. essential for evaluation of the plant under accident conditions. For a listing, refer to letter SNRC-643 dated December 12, 1981.
8.4.1.i The EOF shall be staffed to provide the overall manage-ment of licensee resources and the continuous evaluation and coordination of licensee activities during and after an accident.
Upon EOF activation, designated personnel shall report directly to the EOF to achieve full functional operation within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The EOF staff shall include personnel to manage the licensee's onsite and offsite radiological monitoring, to perform radiological evaluations, and to interface with offsite officials.
l 8.4.1.j Security at the EOF, when activated, is provided by LILCO security personnel under the direction of LILCO corporate
[
security.
Under normal operating conditions the EOF functions as a training center and is secured with standard i
i commercial alarm systems.
8.4.1.k The layout of the EOF was accomplished taking into account good human factors engineering principles similar to those i
described in section 8.2.1.k.
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ATTACHMENT G SHOREHAM REGULATORY CHANGE PLANNING SCHEDULE This schedule delineates LILCO's. plans for implementing regulatory-required post-fuel load modifications.
Non-regulatory based (LILCO initiated) modifications as presently defined will not conflict with this schedule.
Proposed plant modifications are presently documented by Change Control Forms (CCFs).
A tabulation providing a brief description of each regulatory-required post-fuel load CCF is included in the following pages.
Regulatory-required, post-fuel load CCFs are divided into three categories as follows:
Modifications which do not impact Plant 1.
Phase I operations.
2.
Phase II Modifications which impact Plant operations or require a shutdown of approximately two weeks.
3.
Phase III -
Modifications which are extensive or complicated and require a shutdown greater than two weeks.
On the attached schedule, Phase I CCFs have been shown with targeted completion dates.
Phase 11 and III CCFs are denoted with rectangular shaped symbols which are indicative of the magnitude (duration) required for installation of that particular modification.
Ac shown on the schedule, the right end of the rectangle depicts the date at which the engineering and material support activities (design output packages) are scheduled to be completed and installation can proceed contingent upon plant operating conditions and/or expected outages.
Phase II modification design output packages have been scheduled for completion such that these modifications can be installed in a currently defined, preferred sequence as plant operations and unexpected outages of sufficient duration allow.
Phase III CCFs constitute a significant scope of work; they have been scheduled to have design output packages completed no earlier than approximately nine months prior to the start of the first refueling outage.
This lead time is considered sufficient to allow completion of non-plant operations impacting pre-work and proper outage planning.
This schedule was developed based on best available information and predica'ted upon an August 1983 fuel load date.
It should be recognized, however, that Shoreham is not an operating plant having a fixed outage schedule.
Furthermore, other factors exist beyond LILCO's control (e.g. emergency planning) which may affect the ultimate schedule.
Due to this uncertainty, it may be necessary to re-evaluate this schedule.
We anticipate issuing an updated schedule by January 1984 and periodically thereafter as required.
ATTACHMENT G - Page two..
DESCRIPTION OF. POST FUEL LOAD CHANGE CONTROL. FORMS (CCFs)
CCF Number:
Description PM-4A Emergency Response Facility (ERF) TSC, Computer Complex
'PM-4B Neutron Flux Data Points
~
PM-4C Control Rod Position Data Point' PM-4F.
Containment Isolation Valve Position Data Points PM-4V Radiological Parameter Data Points PM-4W Meteorological Parameter Data Points PM-4X Nuclear Boiler Data Points PM-4Y Core Flow Data Points PM-4Z Recirculation Suction Temperature Data Points PM-6A Residual Heat Removal Heat Exchanger Strainer PM-12 High Radiation Auto Closure of AOVs PM-15 Hydrogen Recombiner Component and Rewiring PM-16 Remote Shutdown Panel Addition of Loss of Power i
Alarm and Computer Points PM-20 Reactor Building Standby Ventilation TCVs Actuator Rewiring as 11odified by T46/12 I
'PM-21 Same as Above Except T46/13 l
PM-26 Addition of Circuit Breaker to 1R35*PNL-R2 PM-27A Reactor Protection System Data Points PM-27B ERF Computer Data Points PM-27C ERP Uninterruptible Power Data Points V
PM-27D Residual Heat Removal Data Set
+
PM-27E Recirculation Discharge MOV Position Data Points PM-27F Recombiner Discharge H and O Data Points 2
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PM-27G High Pressure Cooling Injection Data Points i
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ATTACl! MENT G - Page three l
l PM-2711 Reactor Core Isolation-Cooling Data Points PM-271
-Seismic Power Supplies for TSC PM-28 Reactor Building Standby Ventilation Charcoal Filter Trains Wiring and Component Modification PM-29 Remote Shutdown Panel Alternate Shutdown Method PM-30 Recirculation Pump Discharge Valve Actuator Replacement PM-32 Replace Barton Level Transmitters PM-33 Replace Bailey Pressure Transmitters PM-36 Replace MCC Overload Devices PM-43 Scram Discharge Volume Modifications PM-49 Core Spray Low Pressure Permissive Interlock PM-50 MSIV and Mainsteam Drain Valve Set Point Change PM-A* -
Replace Capacitors in Beck Actuators PM-B*
Add Series Breakers to RMS Equipment PM-G*
Relocate HPCI Control Panel to Mild Environment
- Note:
The scope of these CCFs have not yet been fully defined.
Thus, they have not yet been assigned official numbers.
To facilitate identification, they are, in the interim, being assigned a letter designation.
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