ML20206M237

From kanterella
Jump to navigation Jump to search
Insp Rept 50-354/86-29 on 860527-30.No Unacceptable Conditions Identified.Major Areas Inspected:Licensing Action Re Licensee 860513 Request to Delete Fire Protection Tech Specs in Accordance W/Generic Ltr 86-10
ML20206M237
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/18/1986
From: Anderson C, Pullani S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20206M224 List:
References
50-354-86-29, GL-86-10, NUDOCS 8607010103
Download: ML20206M237 (16)


See also: IR 05000354/1986029

Text

___,_ _ _ _ _ _ _ _ _ -

'

.

l

U.S. NUCLEAR REGULATORY COMMISSION l

REGION I ,

I

Report No. 50-354/86-29

Docket No. 50-354

l

License No. NPF-50 Category C

Licensee: Public Service Electric & Gas Company

Post Office Box 236

Hancocks Bridge, New Jersey 08038

Facility Name: Hope Creek Generating Station, Unit 1

Inspection At: Hancocks Bridge, New Jersey

Inspection Conducted: May 27-30, 1986

Inspectors: DllfGnj b -IO - 86

S.VTPt/Ilani, re Protection Engineer date

Approved by: 6 /# d'(,

C. J/ Anderson, Chief, PSS date

Inspection Summary: Inspection conducted on May 27-30, 1986 (Report No.

50-354/86-29)

Areas Inspected: Special inspection in support of a licensing action related

to a licensee request dated May 13, 1986 to delete the fire protection Tech-

nical Specifications in accordance with Generic Letter 86-10.

Results: The licensee's request satisfies the guidances in Generic Letter 86-10. No unacceptable conditions were identified.

.

8607010103 860625

PDR ADOCK 05000354

G PDR

.

__,

.

TABLE OF CONTENTS

Page

1.0 Persons Contacted 2

2.0 Purpose 2

3.0 Background 2

4.0 Inspection of the Fire Protection Programs in Support 3

of the Licensing Action Related to Deletion of the

Fire Protection Technical Specifications 4.1 Incorporation of the Fire Protection Program 3

in FSAR

4.2 Fire Protection Technical Specifications to 4

be Deleted

4.3 Equ valent Administrative and Technical 4

Controls

4.4 License Condition. 6

5.0 Conclusion 7

6.0 Exit Meeting 7

Attachment 1 Standard Fire Protection License Condition on Generic Letter

86-lb

Attachment 2 Proposed FSAR Revision (Enclosure 1 of May 13, 1986 Submittal

Attachment 3 Fire Protection Technical Specifications to be Deleted

Attachment 4 Administrative Procedures for Control of Fire Protection

Program Activities (from Attachment 2 of May 13,1986

Submittal)

Attachment 5 Fire Protection Hardware Categories and Associated ACTION

Statements (from Procedure M-10-FDD-004)

Attachment 6 Action Statement Criteria

1

Attachment 7 Surveillance Requirements for the TS Sections to be Deleted

(from Procedure M10-FDD-005)

Attachment 8 Existing Fire Protection License Condition 2.c.(8)

<

.

DETAILS

1.0 Persons Contacted

1.1 Public Service Gas and Electric (PSE&G)

T. Baileys, Consulting Engineer, Fire Risk Management Inc.

  • R. Braddick, Fire Protection Staff Engineer
  • P. Eldreth, Nuclear Fire and Safety Manager
  • J. Lawrence, Nuclear Licensing Engineer
  • P. Moeller, Manager, Site Protection
  • J. Pantazes, Senior Staff Engineer

.1

A. Saltaka, Nuclear Fire Protection Supervisor

  • T. Storey, Senior Fire Protection Engineer

1.2 Nuclear Regulatory Commission

  • D. Allsopp, Resident Inspector

i

  • Denotes those present at the exit meeting.

2.0 Purpose

The purpose of this inspection was to ascertain that the licensee has

established equivalent measures in support of a licensing action pending

with the Office of Nuclear Reactor Regulation (NRR) with respect to a

recent licensee request to delete certain fire protection program elements

from the plant Technical Specifications (TS). In accordance with the

guidance in Generic Letter 86-10 such deletion is permitted after incor-

poration of the fire protection program into the Final Safety Analysis

Report (FSAR).

3.0 Background

The existing fire protection license conditions for many plants create

difficulties because they do not specify when a licensee may make changes

to the approved fire protection program without requesting a license

amendment. To resolve this problem, Generic Letter 86-10 (dated April 24, i

1986, issued by the NRR to all power reactor licensee's), in Paragraph F,

Addition of Fire Protection Program into FSAR, provided guidance for i

incorporation of the program into the FSAR and subsequent deletion of the

i

i

l

l

__ , . - _ . _ _ . _ . .

. .. ._. - - - -- __ - . . . _ . . -. ._ _

i .

-

i

!

3

i

!

3

associated fire protection Technical Specifications. The guidance also

1

stipulates a standard license condition (see Attachr.>ent 1 to this report)

j to be included in each license. This permits the licensees to make

i

changes to the approved fire protection program after performing a 10 CFR

, 50.59 review and eliminates the need for frequent and unnecessary license

1 amendments in most cases.

!

!

The Generic Letter stated that the best way to resolve the problem is to

incorporate the fire protection program and major commitments, including

the fire hazards analysis, by reference into the FSAR. In this matter,

l the fire protection program, including the systems, the administrative

j and technical controls, the organization, and other features associated

with fire protection would be on a consistent status with other plant

features described in the FSAR.

'

In accordance with the guidance in Generic Letter 86-10 and the precedence

established by Cleveland Electric Illuminating Company fo' the Perry

,

Nuclear Power Plant, Public Service Electric and Gas (PSE&G), by letter

, dated May 13, 1986 addressed to NRR, requested the deletion of the fire

] protection TS and provided supporting justifications for this request.

l This licensing action is currently under review by NRR. This inspection

is in support of the above licensing action by NRR.

j 4.0 Inspection of the Fire Protection Program in support of Licensing Action

,

Related to Deletion of the Fire Protection Technical Specifications

4

) The inspection included a review of the incorporation of the Fire Protec-

I

tion Program into the FSAR, review of the fire protection TS sections to

J

be deleted, and a review of the equivalent administrative and technical

i controls.

. 4.1 Incorporation of the Fire Protection Program into FSAR

J

The licensee's Fire Protection Program (FPP) is described in the

existing FSAR in accordance with the standard FSAR format and the

requirements of the Standard Review Plan (SRP). The description

satisfies the guidance in Generic Letter 86-10 except that the ad-

'

ministrative and technical controls for the fire protection TS items

which are to be deleted are not contained in the existing FSAR. To

delete the TS items, equivalent controls should be incorporated into

the FSAR, either directly or by reference, in accordance with  !

2

Generic Letter 86-10.

I

In Enclosure 1 of the May 13, 1986 submittal (see Attachment 2 of

] this report), the licensee proposed to revise Section 9.5.1.4.2,

!

Operational Testing and Inspection, to incorporate these controls

I (see Section 4.3 of this report for details). The existing FSAR,

together with the proposed revision, satisfies the guidance in Generic

Letter 86-10 for incorporating the FPP into the FSAR.

!

l

3

j

i

-

.

4

4.2 Fire Protection Technical Specification Sections to be Deleted

The fire protection TS sections proposed to be deleted are given in

Enclosure 2 of the May 13, 1986 submittal and are listed in

Attachment 3 of this report. These sections can be categorized into

two groups:

(1) TS requirements for fire protection hardware, i.e., systems,

components and structures ( All TS Sections in Attachment 3

other than TS Section 6.2.2.e).

(2) TS requirement for fire protection organization (TS Section 6.2.2.e associated with fire brigade staffing).

The deletion of these TS requirements is permissible under the guid-

ance in Generic Letter 86-10, provided they are described or refer-

enced in the FSAR and equivalent controls are established. As discussed

' in Section 4.1 of this report, Enclosure 1 of the May 13, 1986 sub-

mittal (see Attachment 2 of this report), the licensee proposed to

revise section 9.5.1.4.2 of the existing FSAR. The proposed re-

visions adequately addresse the equivalent administrative controls

for the first group of TS sections deleted, i.e., the nardware type.

The second group, i.e., the fire brigade organization, is already

addressed in the existing FSAR, Section 9.5.1.5.2 and therefore no

revision to the existing FSAR section is required. (see Section 4.3

of this report for further discussions of the equivalent admints-

trative controls for these items).

Therefore, it is concluded that equivalent levels of controls are

provided for the above TS sections in accordance with the guidance in

Generic Letter 86-10.

4.3 Equivalent Administrative and Technical Controls

The licensee has developed a set of administrative procedures to

control the fire protection program activities. Attachment 4 of

this report is a listing of these procedures. The following

procedures within this set specifically provide administrative and

technical controls equivalent to those currently existing in the TS

section to be deleted:

M10-FDD-001, Fire Protection Organization, Revision 0

M10-FDD-003, Fire Department Manning & Qualification, Revision 0

M10-FDD-004, Actions for Inoperable Fire Protection Systems,

Revision A (Draft) l

l

_. _ _ _ __ _ . __ . _ _ . _ __ __

-

.

i

i

. 5

i

j M10-FDD-005, Fire Protection Periodic Surveillance Test Program,

j Revision 0

i

M10-FDD-008, Fire Protection ' System Impairments.

-

Procedures M10-FDD-001 and 003 together adequately address the 5

member fire brigade membership requirements in TS Section 6.2.2.e

i proposed to be deleted and establish equivalent administrative

!

controls. Hope Creek has a dedicated fire brigade organization

which is independent of the plant operating organization (see

i Procedure M10-FDD-001, Attachment 1). The 5 member fire brigade

requirements are specified in Procedure M10-FDD-003. Furthermore,

l the fire brigade organization is also specified in existing FSAR

j Section 9.5.1.5.2 and the related commitments are clarified in NRC

Supplemental Safety Evaluation Report (SSER)5, Section 9.5.1.3.

l Therefore, it is concluded that equivalent levels of control exist

i for the TS section proposed to be deleted, i.e., TS 6.2.2.e.

i

] Procedures M10-FDD-004, 005, and 008 address the fire protection

hardware type TS sections proposed to be deleted, i.e., all TS sec-

tions in Attachment 3 other than TS Section 6.2.2.e. Procedure

M10-FDD-004 is a new procedure developed to address the Limiting

j Conditions for Operation (LCOs) and ACTIONS for inoperable hardware

d

d

(systems, components or structures) in the TS sections proposed to

be deleted. Procedure M10-FDD-005 is an existing procedure but was

i

modified to include a table (see Attachment 7 of this report) to ,

include the Surveillance Requirements (SRs) in these TS sections,  !

l without any change. Procedure M10-FDD-008 is an existing procedure

j to track the status of the inoperable fire protection hardware until

.

they are repaired and back to operable status. i

,

L

f

The ACTION statement in the existing TS is rather complex and con- l

l fusing to the operator. To simplify this, the new procedure M10-

) FDD-004 regrouped the fire protection hardware into 8 categories (!  !

j through VIII) and developed 9 associated ACTION statements designated '

i by letters (A through I) (see Attachment 5 of this report). These  ;

j ACTION statements are the same as those in the present TS in most

} cases, except that in some cases they are more conservative. The  :

j procedure includes 8 tables (Table I through VIII, corresponding to

i the 8 categories of hardware) which are detailed listing of ACTIONS  :

I

for each individual inoperable fire protection component. The cri-

!

teria used to develop these tables for different cases in the deleted i

TS section are also summarized in the procedure (See Attachment 6 of

this report, Column CRIT., i.e. Critical meaning TS related; note

,

!

j

j that the tables also include NONCRIT, i.e., Non-Critical or non-TS '

related items).

!

i

I

l ____-___ __ ___ _ _ _ _ _ _ _ _ _ _ _

. . . _ _ _ - _ . _ _ _ _ _ __ . _ _ _ _ _ _ . -

__

-

j .

l-

4

,

6

i

l

i

! The licensee has a set of surveillance test procedures in place (see

the list in Attachment 7) to implement the existing TS surveillance ,

requirements. The licensee plans to use these procedures without any

1 change for performing the surveillance testing of the affected fire

i protection sections, even after they are deleted from the TS. How-

} ever, they may be re-designated as Periodic Test Procedures, just to

! distinguish them from those Surveillance Test Procedures required by

TS. These procedures satisfy the testing requirements of the exist- ,

ing TS.

Based on the above discussion, it is concluded that the existing and  !

the new administrative procedures will institute equivalent (or in

{ some cases, more conservative) measures to those TS sections

!

proposed to be deleted.

l

4

4.4 License Condition

i

j The existing Licensing Condition 2.C.(8) will be revised to reference

i latest FSAR amendments and licensee submittals. The revised License

j Condition will be included when the 100*4 Operating License is issued.

The licensee plans to use the following administrative procedures to ,

make changes to the approved fire protection program under the

j provisions of 10 CFR 50.59: '

SA-AP.ZZ-008(Q), Station Design Changes, Test and Experiments,

j Revision 3

i I

.

SA-AP.ZZ-032(Q), Review and Approval of Station Procedures and

A

Procedure Revisions, Revision 4  !

SEI 3.2, Site Engineering Technical Documents, Revision 1

l SEI 4.2, Design Change Control, Revision 2

i SEI 4.3, Design Verification, Revision 0

SEI 4.6, Safety and Environmental Evaluations, Revision 0

These are existing procedures designed to handle all proposed

j changes uncer the provisions of 10 CFR 50.59 and will be used for

'

such changes to the approved fire protection program (FPP) as well.

! These procedures are adequate to determine if a proposed FPP c % nge

! would adversely affect the ability to achieve and maintain a safe

} shutdown in the event of a fire.

li

'

'

i

i

!-

4

!

- ._ _ -.

-

.

7

5.0 Conclusion

Based on the above discussion, it is concluded that:

1. The existing FSAR sections of the fire protection program (FPP)

together with the proposed revision satisfy the guidance in Generic

Letter 86-10 for incorporating the FPP into the FSAR.

l 2. The deletion of the TS sections are in accordance with the guidance

in Generic Letter 68-10.

'

3. The existing fire protection TS requirements are incorporated into

equivalent plant procedures and equivalent administrative controls

exist to control these activities.

4. Adequate administrative controls exist to determine if a proposed FPP

change would adversely affect the ability to achieve and maintain a

safe shutdown in the event of a fire.

.

'

Based on the above, it is concluded that the licensee's request to del r e

1

the rPP elements from the Technical Specifications when the full power

license is issued, meets the guidance in Generic Letter 86-10.

6.0 Exit Meeting

i

The inspector met with licensee management representatives (see Section

1.0 for attendees) at the conclusion of the inspection on May 30, 1986.

The inspector summarized the scope and findings of the inspection at that

3

time.

i The inspector and the licensee discussed the contents of this inspection

! report to ascertain that it did not contain any proprietary information.

, The licensee agreed that the inspection report may be placed in the

l Public Document Room without prior licensee review for proprietary

!

information (10 CFR 2.790).

j At no time during this inspection was written material provided to the

licensee by the inspector.

I

-- __ - _ _ _ _

-

.

l

' -

ATTACHMENT 1

Standard Fire Protection License Condition on Generic Letter 86-10

I

Fire Protection )

(Name of Licensee) shall imolement and maintain in effect all orovisions

of the approved fire protection procram as described in the Final

Safety Analysis Report for the facility for as described in submittals

dated -------------) and as approved in the SER dated ------------(and

Supplements dated ------------) sub.iect to the followino provision:

The licensee may make changes to the approved fire crotection

program without prior approval of the Commission only if those chances

wnuld not adversely affect the ability to achieve and maintain safe

shutdown in the event of a fire.

The licensee may alter specific features of the approved procram provided

(a) such changes do not otherwise involve a change in a license condition

or technical specification or result in an unreviewed safety question

(see 10 CFR 50.59), and (b) such chances do not result in failure to

complete the fire protection program as approved by the Commission. As

with other changes imolemented under 10 CFR 50.59, the licensee shall

maintain, in auditable form, a current record of all such chances,

including an analysis af the effects of the chance on the fire protection

program, and shall make such records available to NRC inspectors upon

request. All changes to the approved program shall be reported annually

to the Director of the Office of Nuclear Reactor Regulation, along with

the FSAR revisions reouired by 10 CFR 50.71(el.

l

_

%

0

, , _ _ _ - , . - . - - - - - - - - - - - - - - . - - - - - - - - - - , - - - - - - - - . - - -, , . , , , , , , , . -- --.., , , - - - - , , - - . - - - -, - . -, --,w~- ,-,

.

7:wEc :

Prcoosed FSAR 9evision (Ecciosure 1 of May 13. '.956 Submittal

9.5.1.4.2 Cperattonal Testing and Inspeetton

  • W ). *

1

n _:: e n: ::11 m e in t19 ef f t re pretectar rytten :nd

_
pr: t c:!! 50 perf er ed i- ::::: den:: -.t' in: epp!:::: :
: :! th: ' :tni::1 !;::+4:::t;:n: 10Mp;;; !! "'00 . CA-'

1

Lf: : :: e-t tasu!!-' !! : fett rel ted :::= cf th: :I n t .

Routtne surveillance testang of the f are protection system an

non-safety related areas of the plant will be performed in

accordance with the applicable NFPA design and installation

standards as modified by the perf ormance history of the equipment

and equipment accessibility.

Y

n:: u::::: p;n-:::t : =,: === ==pectee pe:w emy :-

h- e r!W ter":: 1 !;e!!!1 tirN: i: :::*ete: p = :tect;en

J i-t e;; ; t";

INSERT FOR PAGE 9.5-36

o

Administration controls are provided through existing Nuclear '

Department, Site Protection and Hope Creek Station Administrative

Procedures, Station operating Procedures and the Operational .

Quality Assurance #rogram to ensure that the Fire Protection

Program and equipment is properly maintained. This includes

QA

testaudits of the program implementation, conduct of periodic

inspections, and remedial actions for systems and

barriers out of service. This program emphasises those

elements of fire protection that are associated with safe *

shutdown as described in Appendix 9A and their significance *

when evaluating program and equipment deficiences.

All fire protection equipment and systems are subject to

a complete inspection and acceptance test in accordance

with the National Fire Codes af ter installation is completed.

Af ter the plant is in operation, periodic inspections and

tests will be conducted as defined by the Fire Protection

Program and National Fire Codes. The following fire protection

features will be subjected to periodic tests and inspections: i

A. Fire alarm and detection systems

3. 1eet pipe automatic sprinkler systema .

C. teater spray systems

D. 'Preaction water spray systems

E. Preaction sprinkler systems

F. Carbon dioxide total flooding systems

G.

14 cal application carbon dioxide systems

M. Balon systems

1. Foam systems

J. Fire pumps

R.

Fire barriers (walls, fire doors, penetration

seals, fire dampers)

L.

hydrants)suppression (fire hoses, estinguishers,

Manual

Equipment out of service, including fire suppression, detection

and barriers, will be controlled through the administrative

program and appropriate remedial actiona taken. The program

requires

be all impairments to fire protection systems to

identified. Based on the condition, engineering analysis

may be required to determine the extent of the fire hasard

to safe plant operations. As conditions warrant, remedial

actions would include coepensatcry measures to ensare an

eqatvalent

efforts level of fire protection in additicn to tirely

to effect repairs and restore equipment tc service. ,

.. ._ .-

'

ATTACHMENT 3

Fire Protection Technical Specifications to be Deleted

Section Description Page

3/4.3.7. Fire Detection Instrumentation 3/4 3-9

3/4.7.7. FIRE SUPPRESSIDN SYSTEMS

Fire Suppression Water System 3/4 7-21

Spray and/or Sprinkler System 3/4 7-21

CO2 System 3/4 7-26

Halon System 3/4 7-27

Fire Hose Station 3/4 7-28

3/4.7.8. FIRE RATED ASSEMBLIES 3/4 7-31

6.2.2.e Unit Staf - Site Fire Brigade 6-1

Bases

3/4 4.8.2 Fire Detection Instrumentation B 3/4 3-6

3/4.7.7 FIRE SUPPRESSIDN SYSTEMS B 3/4 7-4

3/4.7.8 FIRE RATED ASSEMBLIES B 3/4 7-4

,

e

'i

l

..

9

_ _ _ _ . _ - . - _ _ ._ - _ . _ _ - . . - . _ _ . _ _ _ _ - _ _ _ _ _ _ _ . - _ - _ _ - - _ - _ - _ - _ _ . - . _ - - - . - - _ _ _-

_ _ _ _ _ _

.. . - -. .

'

.

ATTACHMENT 4

Administrative Procedures for Control of Fire Protection Program Activities

(from Attachment 2 of May 13, 1986 Submittal)

.

NUMBER TITLE

VPN-PLP-004 Fire Protection Program

SA-AP.ZZ-025(Q) Station Fire Protection Program

M10-FDD-001 Fire Protection Organization

M10-FDD-003 Fire Department Manning & Qualifications

M10-FDD-004 Actions for Inoperable Fire Protection

Systems

,

l M10-FDD-005 Fire Protection Periodic Surveillance

1 and Test Program

l

M10-FDD-008 Fire Protection System Impairments .

M10-FDD-009 Hot Work Authorization  ;

\

I

! M10-FDD-013 Violation & Deficiency Reporting  !

I ,

'

M10-FDD-021 Freeze Protection & Winterization of

i

Fire Protection Systems l

2

M10-FDD-022 Fire Department Drills

r

i

M10-FDD-023 Fire Department Training Program

.

i

I l

l

!

!

l

1

e

1 _

- - . - -_ .- - . .. _.

.

.

' "

ATTACHMENT 5

i Fire Protection Hardware Categories and Associated ACTION Statements

i (from procedure M10 - FDD-004)

i Category

'

I. Fire Suppression Systems

I'I. Hose Reels (CO2 & H 2O)

III. Detection Zones l

IV. Fire Barriers

i V. Water Supply System

VI. Fire Doors

VII. Fire Alarm System

VIII. Fire Dampers

)

l

I

ACTION Statements

A. Within one hour establish a continuous fire watch patrol.

. B. Within one hour establish an hourly fire watch patrol.

'

C. Ensure the adequacy of installed portable fire extinguishers in

the affected area or place additional fire extinguishers if

necessary.

i . =:.'s 5'tt'--+' ' :s y e ile :t-' ':1= := '

'

- - = :::u-'-'

i+~;.'.- ::.- r: .: i.

E. Rcute addit cnal hcie from adjacent hcie reels into the sifected

! area uithin twenty-four hours.

'

F. Provide a backup fire pump or water supply within seven days.

G. Pr ovide a backuo fir e pump or water supply within twenty-four

hours.

H. Within one hour establish a daily fire .atch patrol.

!

4

. Evbc.it e .crk order to re; air it.o; er ab l e equipmer.t .

!

I

i

1

1

I

i

i

!

l

l

i

I

h

i

!

.

A

.

ATTAC4WENT 6

Action Statement Criteria

:Leests:1:9.srs:t:.lsceteseLE

CASE e OES;R!a?;0N eg;;;$

CRIT. NCNCm!'.

No aeeran's setectors in t*e area. A e

2 Geer able detectors in the area. A  : C

11 ts0SE.BCEL.itsottle8LE.1CO2 0;. trial

CASE e DESCRIPTION

1 H2O hose reel is primer, fire protection  :

for eree. D  : E

!

2 H 2 O hose rest is secondary fire protection I

for area. E  : 1

3 CO2 hose reel.  !  ! I

!!!. DEIECIl06.1tfGEC966LE

CASE e DESCRIPfl0N

1 he suppression system seerable. O  ! H

t

2 Suppression systee operable. e  : 1

IV. (18C.04881ER.1NDECR4R.E

CASE 8 DESCRIPT!tm ,

8 No detectlen er suppressten available. A I C/1 '

i

2 Detection avellette en one side. 9 I C

3 Detectaen avait ante both sides. H '

v. WeIER.$uttLY.1W0ttlesLE

CASE e DESCR1pfl0N

one pune/ reservoir unevettable. P  : r

2 two poses / reservoirs vaevantante. a  : o

V1. tite.0008.1W0ttle8LE

CASE e DESCRIPf!ON .

1 No detection er supprettien evetlable. A  : t/c

2 Deteettaa avallette one side. 8 C

3 Detection evantable both sides. H i  !

l

.

v!!. EltE.6Letc.SYSIED.llf0ftte0LE

CASE e DESCRIPfl0N

1 OC671 panel inoperable. t

2 Seettfit f/R inoperante.  :

vill. Eltt.Deeftt.itf0ttletLE

Cast e DESCRIPfl0N

'

1 N3 detICI10m er swePression availab'e. A l/C

Oetect4aa avaa'abte ano stee. I C

3 Cetectsen availante tota sides. H  !

_ .- _. .

.

+

f

4

s

ATTACHMENT 7

Surveillance Requirements for the TS Sections to be Deleted

(from Procedure M10-F00-005)

'

i

r,ti,

t.s. see. F.es.

ggget

,, .t e,

133 3333333333333

22888337211185t2888288884t&t2238184t48333 4.7.7.1.1.. 007 0

354828131188888 F r e wate, sie,ese reai te.et ver. 031 0

evee Deer feet a .7.7.1 1.t

Electric Meter Dee.ea Fre d . 7. 7.1 1.< L!! *

M10 $>t 002

P10 $wt-00?

1 $ Fire heter ve1.e tiae.e Ve*e8 4.7.7.2.e O!! O

4.7.7.3.1.4 012 P

1, ster F l e e *,

P;C 1=?-C04 Fece f.sresoser. Late. 4.7.7.1.1.I.2 (19 P

I are Ives Arewe' Cat es ety Test 4.7.7.1 1.8.4 016 P

P10-!Wi=004 4.7.7.1.1.e 012 e

psee kate $ eten vet.e Cv<1 at 5.*ves11em e d.7.7.1.1.4.3 01t m

F10 $wt 007 3. 7. 7.1.1. $ 007 *

Pj'a!***00$ F ir e Pe if I'en Tet* Fere F es (te' *est 4.7.".l.!.e.1 031

beest, Liesel Ortver. 4. 7.7. t . 2. 6. ; 0:1 0

M1(.-$.t 004 4.7.7.t.2.4 De: C

Geo ter1, Dieset Fie e Fvas eve * Oil lessle 4.7.7.1.3.e C07 0

d

tw 16.II 0!!<C) Ween tv Diesel F are P. o tetter v f est 4.7.7.1.3.6 09; O

M0 $ t .tC 00 t e F ) Geer ter ly Diese) Fsee P. r Betteryfeet feet 018 r

MD tt.FC-002tF1

4.7.7.I.3.c

If Montti Diesel Fire Fuas letter , 4.7.7.1.2.c 019 P

MC.$f.EC-003tF) a.7.7.1 1.e 012 M

MC FM.ut 00tt03 18 terDieset

e, t DelvseFiretrotFoss

Funct test t lass

f atiae taan Olt M

',

M10-$Mf-015

Water 4.7.7.1.1.f.I

d 7.7.2.b 012 M *

4.7.7.1 1.f.3 Ott M

4.7.7.2.t Ott M

4.7.7.I.t.t.1 Olt M

,

Preettien Seelanter Svet Fuact feet L laen 4.7.1.2.b 012 M

M10 $Hf +016 ott M

4.7.7.2.c

4.7.7.l.I.e 012 M

1 Preaction Water torov Svet Fenet test i tase a.7.1.1.1.f.! 018 M

M10 SHf-017 012 M

i 4.7.7.2.b

'

4.7.7.1.t.f.3 018 M

d.7.7.2.e Ott M '

4.1.7.2.4 00? t

f Fle= test 031 0

j M10 SMi-019 fr iennial Delvee seria6ter 4.7.7.3.1

f

17 fea CD 2 $,et Fle. Peth Ver sf 4.7.7.3.2.s 007 0

M10 SM1 019 *

!

M10-$NT 020 17 f ea CO 2 S vet Stor ese Level & Pr es. Vet ti 4.7.7.3.2.6 038 M *

17 fea CO 2 Svet Opereb & Per t Discheroe 4.7.7.1.s 031 0

M10 SM1 021 018 M -

4

M10 $MT 022 7 $ Fire Hese stetsoa Vsevel laneettien 4.7.7.5.6 -

Fire Heee Stet ten Detested lastettien a .7.7.$.t .1 003 7

,

M10 SMt 023

'

M10 tMt 024 Fir e Mene Statiea Fie. Ver sticat een 4.7.7.5.t.2 003 Y

F ire Mese St at een M,4r estet ic f eet d.7.6.1.c 018 M

M10 tat 025 0:# *

it meet* F ie e t s** ies Feaetesties lastettisek.*.f.2

est !** C's

8 *e *s:- Irete.t.e* !. .e. 'e*:e 4 . 7 . t .1.1 C*f -

et* t ***!*

le me *te 8.ee*+=

vie.et  !*stetteer 4.!.7.t,1 C* *

i *10 5*' 004 sea Ara.el Fsee sete:tiea OseaOsatteitit, test 006 M

M10 tat-0 9 feet d.3.7.4.2

seen Ann.et Sveer wased C ae tvs t d.7.7.2.6 012 M

4' P10 $M1 030 Wet Pipe Seria61er $ ret Fuact feet 4 ! ass Ott M

M10 lM1 034 4.7.7.2.t

013 M

(seessac, L es*t aat levisevat f eet & lan a.7.7.d.6 018 M

1 P10 1M1 039 Ott M

M10 $NT 048 le Meat > Hetea tvete Aee Fle. Test 4.7.8.l.e

le Meata fiee 6eetier laes es t soa 4.7. 8. 2 . t- 001 0

mig $NT 056

Revia, Peteet a.7.0.2.s 024 M

M10 tM1 058 012 M

d.7.7.1 1.e

M10 twi+060 Freettien Svet tPl4 Fva ttseaal feet & lass a.7.7.1.1.f.1 Ott M

d.7.7.2.6 012 M

ei, .

4.7,.7.2.,

, 7. : . , 0 , . ,.

te,. i :..,

.t...
n i.e.  ::t ..,n ,..si

'[:i, lC,

.. . ;

.e .e., $..e..., ...,

.

.

.1 ces ..t.. i. ..

, ,, .e,.

,...,,,,

i: 1 ..:,.

-

.e o. l..... e,.

,,,,,,, , , y,,

l ri,,. 1. e... . , .eie,

i.e,,es,,,,,,,..,

.:c.i. c.-

3.e.,, vat., o ,,,

-

'.1,;,t,,;

gll

,i: iMne.t ... tai, , 0,, ,

.,..,,,,,e,ec :,,e Dete n te, F.a t,6ast ves, 4.3,,,

ta.c.n mg., F ., i t feet

gg y

>e t t* m...

'80*lM It acett (ee., siget,ag (

'

1

.

f

.

__ _ _ __ - -

ATTACHEMENT 8

,

Existing Fire Protection License Condition 2.C.(8)

(8) Fire Protection (Section 9.5.1.8, SSER No. Si

DSE&G shall implement and maintain in effect all nrovisions of the  ;

approved fire protection program as described in the Final Safety

i Analysis Report for the facility through Amendment No.13 and as

described in submittals dated August 12 and 27, November 21 and 29,

December 3 and 16, 1985 January 3, and April 8,1986, and as

approved in the SER dated October 1984 (and Supplements 1 through

j 5) subject to the following provision:

.

The licensee may make changes to the approved fire

protec+1on program without prior approval of the

Connission only if those changes would not adversely

affect the ability to achieve and maintain safe

shutdown in the event of a fire.

!

!

i

i

i

l

l

a

i

i