IR 05000400/1986027
| ML18003B249 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/12/1986 |
| From: | Conlon T, Wiseman G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18003B248 | List: |
| References | |
| 50-400-86-27, NUDOCS 8605200194 | |
| Download: ML18003B249 (14) | |
Text
~gIt AE0Ir, (4 fp,0 A.
O
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report No.:
50-400/86-27 Licensee:
Carolina Power and Light Company
,
P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Harris
Inspection Conducted:
April 14 - 18, 1986 I
Inspector:
G.
R.
Wsseman Approved b
T. E.
Con on, Section C
>e Plant Systems Section Division of Reactor Safety License Noe I CPPR-158 Date'Soigne te Signed SUMMARY Scope:
This routine, unannounced inspection involved 38 inspector-hours on site in the areas of fire protection and prevention and the licensee's implementation of the fire protection commitments for the special nuclear materials (SNM)
license for receipt of new fuel.
Results:
No violations or deviations were identified.
BLt,ogg00194 86 POP ADO@K 050 pDJR
m pl L
tp I
rt I
I lf I
REPORT DETAILS Persons Contacted Licensee Employees
- N. J. Cheiangi, Manager, Quality Assurance/Quality Control (QA/QC)
Harris Project
- G. L. Forehand, Director, QA/QC
- S. Hardy, Harris Project Engineering Support (HPES) - Fire Protection
- J. L. Harness, Assistant Plant General Manager
- D. L. Markle, Operations Fire Protection
- G. A. Meyer, Project General Manager - Completion
- D. A. McGaw, Superintendent, QA
- G. L. McKenzie, Acting Director, QA/QC Operations
- M. R. Oates, Principal Engineer, Nuclear Licensing
- J. F. Pinto, Harris Project Engineering Support - Fire Protection
- C. E.
Rose, Jr.,
QA Supervisor, Operations
- J. H. Smith, Operations Support Supervisor
- G. M. Stokes, Operations Fire Protection
- R. A. Watson, Vice President, Harris Project
- J. L. Willis, Plant General Manager Other licensee employees contacted included construction craftsmen, engineers, technicians, operators, mechanics, security force members, and office personnel.
Other Organizations
- M. Branch, Daniel Construction, Safety/Fire Protection J.
P. Kirk, Daniel Construction, Project Administrator D. Sadler, Daniel Construction, Mechanical Test Discipline Engineer NRC Resident Inspectors
- G. Humphrey
- G. Maxwell
- Attended exit interview Exit Interview The inspection scope and findings were summarized on April 18, 1986, with those persons indicated in paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspection findings listed below.
No dissenting comments were received from the licensee.
a.
Unresolved Item (400/86-27-01),
Possible Deviation From a Commitment on Fire Barrier Separation of Fuel Handling Building for Receipt of New Fuel - paragraph I tL i h
M
'h W
4',
M M ~
P I
>>
M I
~
I IM II M
W 4,
K IK4 \\
I I'
A f'
A
~
W
~
~
IK
~
-
~
~
=
~
M S
~
"
MW M q I 'h M
I'l A
Ii P>>
I
>>M'I '
p h
- ltj jl K
~
jj h
~
M" f II
>>I, F II I
,
A l'tht I'I
. lh
~ Pglth ~
W
~
M s h
II 44K I ~'K4
- I
b.
Inspector Followup Item (400/86-27-02),
Completion of Preoperational Testing of the Fire Pumps - paragraph 6.a.
c.
Unresolved Item (400/86-27-03),
Implementation of the Operations Phase Fire Protection Program Within 90 days Prior to Fuel Load-paragraph 6.b.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or deviations.
Two unresolved items identified during this inspection are discussed in paragraphs 5 and 6.b.
Fire Protection Program for Nuclear Material Storage (License (SNM-1939))
Shearon Harris Nuclear Power Plant, Unit No.
1 - Docket No. 70-2997, Special Nuclear Material (SNM) License No.
SNM-1939 was issued to the licensee by letter, dated October 28, 1985.
The licensee's fire safety commitments are described in Section IX of the Safety Evaluation Report (SER),
dated October 28, 1985.
New fuel receipt is scheduled to begin May 1, 1986.
The SER was used in this inspection to determine the fire protection commitments and requirements.
The inspector conducted a tour of the Fuel Handling Building (FHB).
The SER states that the FHB is separated from other structures by 3-hour fire barriers.
The licensee's plan for fire barrier separation of the new fuel storage areas upon fuel receipt includes establishment of fire barrier separation for portions of Fire Area 5-F-BAL including the unloading bay ( Fire Zones 5-F-3-SC, 5-F-2-SFA, 5-F-3-CHG, 5-F-3-HV at elevations 237 ft.
and 261 ft.);
the operating floor (Fire Zones 5-F-4-BAL, 5-F-3-NF, 5-F-23-NFP2, 5-F-23-FTC2, 5-F-23-SFP2);
and associated stairwells connecting these zones.
The inspector's walkthrough of the above areas indicated that the separation was being completed except that no fire damper was installed at the Fire Zone 5-F-3-NF barrier for the ventilation path to the change area of Fire Zone 5-F-3-CHG.
This duct, however, was continuous through the barrier and combustible loading in the zone is minimal.
Based on this information, this unsealed penetration appears acceptable.
At the time of the inspection, numerous electrical penetrations had not been sealed at the fire barrier.
The licensee s overall fire barrier separation plan for fuel receipt, as reviewed by the inspector, appears acceptable; however, it does
~
~
It
h tt
't rt r
f=I t
t i4+I
~ t I
r ~
,1 II I
I II I'
N tf I'
~
I 4
~,
I',
4 tt1 r t'
~ (l
W
~
,,fM 1I
I
NI K, ',,
'JJ I'
N
NC N A F
C I
WKNI '
not agree with the description as denoted in the SER.
This discrepancy was pointed out to licensee management during the inspection.
On April 16, 1986, th'e licensee issued a letter to NRC/NRR to provide clarification to the SER.
This discrepancy is identified as Unresolved Item (400/86-27-01),
Possible Deviation from a
Commitment on Fire Barrier Separation of Fuel Handling Building for Receipt of New Fuel, pending NRR review of the April 16, 1986, clarification letter and issuance of a supplemental SER for fire safety.
The SNM SER states that hand portable extinguishers, standpipe hose stations, and manual fire alarm stations with local alarm and annunciation in the control room are to be provided.
At the time of the inspection, the hand portable extinguishers were not installed in the fuel storage area.
The licensee stated that these would be installed prior to receipt of new fuel.
The interior fire hose stations in the new fuel storage area were found complete and in service.
The following hydrostatic test records for fuel handling building standpipe and hose system were reviewed and found satisfactory:
Test No.
6175-FP-038
~Oi N.
T <<gAAlC R CAR-2165G056 4-1-86 4-2-86 The inspector verified that the manual pull fire alarm stations in the fuel storage area had been installed; however, the alarm and valve position zone circuits at the local fire detection control panel (1-LFDCP-13), the main fire detection annunciation panel (NFDIC) in the communications room, and the main control room annunciators were not complete at the time of the inspection.
These circuits are to be completed and tested prior to receipt of fuel.
The following control and isolation valves to the fuel handling fire hose systems were reviewed:
Valve No.
Valve T e
PI V-FP-77 8FP-V-75-1-4 8FP-V-72-1-4 8-FP-V-185-1-4 8-FP-90 8-FP-91 8-FP-92 8-FP-93 PIV-FP-125 Yard Isolation Valve Control Valve Control Valve Control Valve Control Valve Control Valve Control Valve Control Valve Waste Process Building Feed Isolation The valve positions were verified to be in the correct designated positions; however, procedures for surveillance and position control of the valves to the Fuel Handling Building hose system had not yet being implemented.
The licensee stated that these valves would be added to inspection procedure
I I
ft A
<< ft ~ a V
l 4" W
I lrv A
H
JN,f tt,WH 4'l'
$1<<
~t ~
II
I Hl I
II Htg it<<
"A I
"WV H il H,W ff
~
'
I'<<1,
<<
P I
,'I 4
<<,'ll J
4
C
~ <<Ha l 't g
<<l,t
4/',f
~ tii H
t 111 r
W 4 it H
"4 h
N
'I q<<
~
I'"I I
NIW I H<<IV l'
I( *
Nit fi IN a
H Il
'
,<<'r H
N,
.4 Hi HI H
i lt'
'"
ft
OST-3002, Main Valve Verification, and that future inspections would verify that the valves were in the correct positions.
These inspections will be performed on a weekly basis until the electric valve position system is completed for the fire detection system.
The licensee committed to implement this action prior to fuel receipt.
This will be reviewed during a
subsequent NRC inspection.
The inspector reviewed the Operations's Department pre-fire plans which have been developed and issued for the new fuel storage areas of the Fuel Handling Building.
Other operation s fire protection administrative control procedures were reviewed during a previous NRC inspection and are addressed in NRC inspection Report No.
50-400/85-40.
Based on these reviews, it appears that the procedures meet the NRC guidelines.
However, the inspector expressed concern that the procedures had not yet been implemented for the new fuel storage area.
During the exit interview, the license committed to implement those portions of the operational fire protection program applicable to the new fuel storage area and new fuel handling activities prior to the receipt of fuel.
6.
Permanent Plant Fire Protection Features a.
Fire Pumps (Module 64053B)
An inspection of the electric-motor and diesel-driven fire pumps located at the emergency service water screening structure indicated that the pump's installation was essentially complete.
A review of the fuel oil supply for the diesel driven fire pump indicated that installation of a drainage system for the curbed fuel oil containment barrier was completed as identified on FCR-SAP-113 and meets the requirements of NFPA-30, Flammable and Combustible Liquids Codes.
The fire pumps have been turned over to the startup organization.
Review of the licensee's startup procedure status report, dated April 15, 1986, indicates System Flush (Procedure No. F-Ol),
System Hydrostatic Test (Procedure No.
H-01),
System Checkout (Procedure No. 0-01)
have been completed.
However, the final acceptance preoperational tests on the fire pumps (Procedure P-Ol)
has not been completed.
This testing is presently scheduled for completion in June 1986.
Pending review of this test data, this item is identified as Inspector Followup Item 400/86-27-02, Completion of Preoperational Testing of the Fire Pumps.
b.
Fire Prevention Administrative Control Procedures (64704)
The NRC Region II review of the licensee's operations phase fire prevention/protection administrative control procedures is documented in Inspection Report No.
50-400/85-40.
The licenses has not yet implemented these procedure e[
~ ~
J H
I'
ff'
Ml I
>>
HM I I,
I H
I Qth',
!'
h>>w ihkw J>>.'j," I f
~
Iv I
J jl J ~
I t
'I Ii I
P I r Iw H
.JI '
~
H J I M
il
~
I P'i P
li P,
Hw I!
I V
M III MII
-'j,ff/
hff I
Ih M
I l,
P PM w
M"II'I.
a H
I'!
j jj Ih H
li R
h*
H t ~
M M
f>> I I P
(I w
I
! e s,
n
~ l a
M tj M
R
~ Hf'
~
'
P, jj
'
Ml'Hhi hi'
~
II t
JIll
~
M
I g'P)
~ I hd v
~ >>
'
The SHNNP Fire Protection gA Program for the Operations Phase is controlled by the policies and requirements of the Corporate guality Assurance Program.
FSAR Section 17.2.2. 1 requires the Corporate gA Program to be implemented at least 90 days prior to fuel loading.
Fuel load is presently scheduled for July 1986; therefore, it appeared that the fire protection program should have been implemented.
This concern was presented to the licensee and is identified as Unresolved Item (400/86-27-03),
Implementation of the Operations Phase Fire Protection Program Within 90 Days Prior to Fuel Load.
The status of this is being maintained by the site Resident Inspector and will be reviewed during subsequent NRC inspections.
7.
Inspector Followup Items ( IFI)
The licensee's actions on the following IFI's were reviewed:
a ~
(Closed) IFI (400/84-26-01),
Review of Fire Protection gA/gC Program to Address Accessibility/Operability and Design Requirements of NFPA Fire Codes:
The licensee has developed an inspection walkdown procedure through issuance of FCR/FP-012 on December 6,
1984.
This procedure requires that all hose stations be reviewed for a clear area envelope around that hose rack to provide accessibility and a clear swing area for the rack and fire hose.
Corrective action is taken when any obstructions are identified.
i b.
c ~
d.
(Open)
IFI (400/85-40-02),
Revisions Required to Fire Protection/
Prevention Procedures in Order to Meet NRC Guidelines:
The status on the three parts of this item is:
(1)
FPP-l, Rev. 3, Section 5.19 addresses the prohibition of smoking in safety-related plant areas included certain posted areas.
This appears acceptable therefore, this portion of the IFI is closed.
(2)
5 (3) Revisions to Procedure TI-105 have not yet been approved; therefore, this items remain open.
Closed)
IFI (400/85-40-03),
Incomplete Operation Surveillance Test OST) Procedures for Fire Protection Features:
The license has revised the OSTs to include surveillance for fire protection valves, fire hose stations and fire hose valves which are included in the Technical Specifications.
In addition OST-3006 Revision I, Section
now provides for proper valve alignment to allow for correct flow paths to accomplish the fire main flow test.
(Closed)
IFI (400/85-40-07),
Engineering Analysis, Testing, and Justification for Non-Standard Penetration Seal Configurations:
On February 13, 1986, the licensee issued Engineering HPES Instruction 7.6.L, Revision 0, Penetration Seal Report Guidelines, to provide program guidelines for engineering justification and documentation for penetration fire seal configurations.
The inspector reviewed documentation package FCR/FP-255 R-I for penetration seal P-3953.
The
~ frk F
Ilk
>>
lf (
~
~
w, k
WW C'w F
r l,
f l
W kk F
~'Il lf ll II I
W II I
II I
I"
'
rl I
4kr
'I Il>>
- i f
>>1 If
~
Wik,'>>
"'>>14 P
fl wk
.)'<<'>>
Ã. kl r>>
1t'
T
~r
,.k fl >>kl'
l Ir ~
IW
<<
~
~
If I
t ll I
~
~
Fll 4
, I
FCR indicates that the box-out damming board configuration for this seal is similar to an approved and tested configuration as shown on the manufacturer's drawing A-246-11.
Based on this review, the program appears acceptable.
Documentation for other specific seal configura-tions identified under this program will be reviewed during future NRC inspections.
(Closed) IFI (400/85-40-08),
Revisions Required to Fire Door Inspection Procedures to Meet NFPA Standards:
Inspection procedure TP-70, Revision 2, dated April 7, 1986, has been issued to include inspections to verify the free swing of fire doors for a full 90 degrees by the automatic closure mechanism and the presence of astragals on double leaf doors.
Fire door latch engagement depth is not addressed because the licensee stated that builders type door hardware was installed and that latch engagement depth does not apply to this type of hardware.
The procedure does however, require that the door close and remain securely latch.
This is acceptable.
Inspection reports which implement procedure TP-70 for fire doors in safe shutdown areas of the plant will be reviewed during a future NRC inspection.
(Closed)
IFI (400/85-40-09),
Piping to Automatic Sprinkler System and Interior Fire Hose System For Diesel Generator Building Fire Suppression Systems Is Not Designed To Meet Single Failure Criteria As Required By FSAR:
The licensee has issued (Review Approval Form)
RAF-HPES-639 to revise the FSAR to more accurately describe the fire protection system installation in the diesel generator building.
The RAF indicates that the new hose stations added by the field change are an enhancement to the system and that the design complies with the requirements of BTP-9.5. 1.
This appears acceptable.
(Closed) IFI (400/85-40-12),
Two Fire Pumps Are Not Provided For Supply To SSE Interior Fire Hose System:
FCR-P-4910, Rl was issued on March 14, 1986, to delete the SSE booster fire pump from the plant design and provide the fire protection water supply for the post SSE fire hose system from the (essential service water)
ESW booster pumps 1A-SA and 1B-SB discharge header.
RAF-HPES-705 has been issued to amend the FSAR to describe this design change.
Upon completion of work for FCRP-4910,R1, this installation will be reviewed on a subsequent NRC inspection.
(Closed) IFI (400-85-40-13),
Reactor Coolant Pump Oil Collection System Is Not Designed To Maintain Structural Or Pressure Integrity Following A
SSE And Was Not Constructed Under A QA/QC Program.
Technical Memorandum TM009 was issued on April 10, 1986, which provides the licensee's engineering evaluation of the reactor coolant pump oil collection system.
The evaluation concludes that the system was designed, installed, and inspected per site requirements for Non-"Q" seismic supported systems with a stress analysis (FCR-M-1212R5, hanger design)
which provides a
system that is seismically supported in accordance the CP&L commitments as stated in their October 14, 1983 letter to NRC/NRR (LAP-83-479).
Based on the inspector's review of the above, this conclusion is correc H
~
~
I'
l t
l I
ii
~I, Hy Mjj h
v l
ii
)
k" 1'
Ii
Ct t 4 Mh i
r Ch
~))
Iv. Hy 'r M
H V
H It
4 j lip EM V
4
~ '
'll
lt H
I.,
t
, f
~
V It H'l HII, l )
y H
I V-
"ii'
I Hh
)
~ >>
~
'My "
O'H VI t
h t
E r
EC I
)Hl tt II
'lC "
H E
4 'y t
ll
~
~
- ~
4
~
~ f iiH V
,
ll'
'I I
H l I
l lt..,
4 Ii 'i l
H, F I
~, h y
~
I
~ 4 H
E
li
~
y M f r/L.t
y E'H (
r v'I Ml 1 II h*h C'4'I y ey I I
.)4
MI 1,
I
) I~j
~
ijl p
'" lH:
4)'
H~VHE yhy