IR 05000302/1978006
| ML19317G355 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/30/1978 |
| From: | Dance H, Wessman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317G339 | List: |
| References | |
| 50-302-78-06, 50-302-78-6, NUDOCS 8002280954 | |
| Download: ML19317G355 (12) | |
Text
_ __
_ _ _ _ _ _ _ _ _ _ _ _- _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
.
.
.
- gm ne49[o,,
'.
UNITED STATES
'
NUCLEAR REGULATORY COMMISSI.
-
o REGION 11 (
. :. t 230 PE ACHTREE STREET. N.W. SulTE 1217 I
ATLANTA, GEORGI A 30303
%
o
%...../
~
.
Report No.:
50-302/78-6 Docket No.:
50-302 License No.: DPR-72 Licensee: Florida Power Corporation 3201 34th Street,. South P. O. Box 14042 St. Petersburg, Florida 33733 i
Facility Name: Crystal River 3 Inspection at: Crystal River site, Crystal River, Florida Inspection conducted: March 13-17, 1978 Inspectors:
R. H. Wessman T. J. McHenry Reviewed by:
6%
Y i
H. C. Dance, Chief f Date Reactor Projects Section No. 1 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on March 13-17, 1978: (Report No. 50-302/78-6)
Areas Inspected: Routine, unannounced inspection of plant operations and outage activities related to fixed burnable poison rod assembly failures; review of procedure administrative controls; followup on reportable events; followup on previous noncompliance items; followup on
IE Bulletins and Circulars; and facility tours. The inspection involved 76 inspector-hours on site by two NRC inspectors.
Results: Of the six areas inspected one item of noncompliance was
_
identified in one area (Infraction: Failure to follow administrative procedures governing usage of plant procedures (78-06-01).)
.
8002 280 fN
.
a en-ac
..
em g
.-.
-. _. -
.,.,.e,
.,.
s-4%
r.
. - _ _. - -
-
.
.
-
,
g RII Rpt. No. 50-302/78-6 I-1 DETAILS I Prepared by:
N.
h.- # -
3Nobf R. H. Wessman, Reactor Inspector
'Date'
Reactor Projects Section No. 1
~
/
Reactor Operations and Nuclear Support Branch Dates of Inspect on:
rch 13-17, 1978
,
Reviewed by:
k 7f H. C. Dance, Chief Date Reactor Projects Section No. 1 Reactor Operations and Nuclear Support Branch 1.
Persons Contacted Florida Power Corporation (FPC)
- G. P. Beatty, Jr., Nuclear Plant Mr. nager
- W. R. Nichols, Operations Superintendent
- P. F. McKee, Technical Services Superintendent T. C. Lutkehaus, Performance Engineer Supervisor
-
\\
W. R. Klein, Reactor Engineer
- J. Cooper, Compliance Engineer
- G. M. Williams, Compliance Plant Engineer
- G. R. Westafer, Maintenance Superintendent
- P. D. Breedlove, Office Manager
- H. B. Lucus, Administrative Supervisor T. H. Wayble, Nuclear Shift Supervisor C. G. Goring, Compliance Auditor G. L. Claar, Compliance Auditor W. A. Cross, Plant Engineer J. N. Kc-tz, Plant Engineer W. C. Pit tman, Mechanical Supervisor
- Denotes those persons present at Exit Interview.
2.
Licensee Action on Previous Inspection Findings a.
(Closed) Noncompliance Item 78-2-01, Control of Plant Clearances.
The inspector revievad the licensee's controls for plant clearances for 4Lplementation of corrective actions described in the FDC response (dated February 21, 1978) to the NRC's Notice of Violation issued February 2, 1978.
The inspector O
.
m
<
v
-
m
.
.
,
,
O y,y RII Rpt. No. 50-302/78-6 I-2
_
_
reviewed the Compliance Section Audit of Plant Clearances and Safety Committee Meeting Minutes of January 24, 1978, documenting-
,
corrective actions taken.
Inspection of selected clearances (c.f. paragraph 8.c to Details II of RII Report 50-302/78-4)
revealed no discrepancies.
LER 78-006/03L-0, Incorrect Tagging of MUV-25, was closed in conjunction with this review.
,
b.
(Open) Noncompliance Item 77-21-01, Failure to Follow Maintenance Administrative Procedures.
The licensee has taken steps to correct discrepancies in maintenance administrative controls.
Since additional discrepancies exist, as described in paragraph 11, this item remains open.
l 3.
Unresolved Items j
Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations.
One unresolved item, relating to record retention, was identified (78-06-02).
Technical Specification 6.10, Record Retention, specifies the g
minimum retention period for certain plant records.
Inspection of
'
selected records indicated that records are being retained within the require. ants of the Technical Specification. However, record retention is presently controlled by NUS Corp. Manual 1833 which, in many cases, specifies retention periods which differ from the Technical Specification.
The licensee acknowledged the inspector's comments regarding this item.
This item will be reconsidered on a future inspection.
4.
Exit Interview A meeting was held by R. H. Wessman with G. P. Beatty, Jr. and
--
members of his staff on March 17, 1978.
Items covered by this inspection were diacussed, including a new noncompliance item concerning implementation of procedure administrative controls and an open noncompliance item relating to maintenance administrative controls.
The licensee also identified organizational changes made pursuant to Proposed Technical Specification Change No. 15.
These changes
'
have been made, with the approval of Nuclear Reactor Regulation, prior to issue of the approved technical specification change to facilitate the organizational transition and update of facility documents.
Significant aspects of that change are:
.
-_. - _ _
_ _ - _ _ _
.
. _ _ _. _ _ _ _ _
l
.
.
-
,
q
,
RII Rpt. No. 50-302/78-6 I-3
-
'
W. R. Nichols is the Operations Superintendent (vice Operations Supervisor)
G. R. Westafer is the Maintenance Superintendent
.
P. F. McKee is the Technical Services Superintendent T. C. Luckehaus is the Performance Engineer Supervisor J. Cooper is the Compliance Engineer (replacing D. Pedrick, IV)
t 5.
Plant Procedures The inspector reviewed selected copies of the licensee's procedures.
Procedures were reviewed for cc sliance with Technical Specification 6.8 and AI-400 (Plant.Operati'
Quality Assurance Manual Control
Document). Selected procedur included Operating, Abnormal, Emergency, Maintenance, Surveillance, and Administrative procedures.
The following discrepancies were identified in implementing the requirements of AI-400 for the licensee's procedures:
Annual reviews had not been performed on various procedures a.
including the following:
- EM-201, Duties of Individual Who Discovers an Emergency
~
EH-205, Evacuation and Personnel Accountability of CR-3
-
,
'
Personnel EM-208, Duties of Radiation Emergency Team
-
MP-101, Pressurizer Spray Head Removal and Replacement
-
,
"
MP-103, Freeze Seal for Nuclear Piping Systems
-
F/-105, Filter Removal and Replacement
-
EP-101, Unit Blackout
-
EP-102, Loss of Containment Integrity
-
0F-406, Spent Fuel Cooling System
-
b.
A review of SP-320 (Operability of Boron Injection Sources and Pumps), which was affected by Amendment No. 8 to the Technical Specifications indicated that a procedure change had been made
,
to conform to the Technical Specification Amendment.
However
,
this review of SP-320 was not documented, as required by AI 400.
'
Further investigation of other procedures indicated that reviews and changes made as a result of Technical Specification changes, design modifications, or unusual occurrences, were not documented.
l c.
The following discrepancies in implementation of temporary
,
procedure changes were identified:
(1) Temporary changes to OP-209 (Plant Cooldown) and OP-204 (Power Operation). dated March 1, 1978 and February 12, 1978, respectively, were not entered in the Working Copy control room consumable file of procedures.
I l
l
, - -.-
- - - -
- -
- -
-..-..
-
- O RII Rpt. No. 50-302/78-6 I-4 (2) Temporary changes to OP-303 (Draining and Nitrogen Blanketing of the RC System) dated May 15, 1977; and to OP-401 (Core Flooding System), dated February 16, 1977 and January 28,
-
,
1977, should have been rescinded but were still in effect.
(3) Temporary change to OP-401 (Secondary Services Closed Cycle Cooling System), dated November 23, 1976, was rescinded December 23, 1976,'but the control room procedures still had the temporary change in effect.
d.
Enclosures to procedures (and separated from the controlling procedure) were being used in the plant to perform plant evolutions. Enclosures were not stamped " Working Copy" and no written administrative system exists to specify the method of control of these enclosures. Procedures with uncontrolled enclosures included the following:
.
SP-301, (Shutdown Daily Surveillance Log)
-
SP-300, (Operating Daily Surveillance Log)
-
SP-340, (ECLS Pump Operability)
-
SP-344, (Nuclear Services Cooling System Operability)
-
O SP-345. (Auxiliary Building Ventilation Exhaust System-l
-
Monthly Test)
These above four items have been identified as an infraction in the Notice of Violation (78-06-01).
6.
Observation of Outage Activities
'*
'
The inspectors observed various portions of the outage activities on both day and evening shifts during the week of the inspection.
Activities relating to the assessment of steam generator tube
'
damage were observed.
The inspector observed portions of the licensee's inspection of the plenum and reactor internals and activities related to retrieval of the damaged burnable poison rod assemblies.
7.
Facility Tours The inspectors toured portions of the facility on both day and evening shifts during the week of the inspection.
Several minor
,
housekeeping items were identified to the licensee (78-06-03):
i l
a.
A considerable quantity of low level solid waste was stored in l
the waste drumming area in yellow poly bags.
The licensee (
stated that this material was to be compacted and drummed for i
shipment within a few weeks.
-
.
.
_ _ _ - _ _
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _.
.__
..
.
-
O).
\\
\\~ '
RII Rpt. No. 50-302/78-6 I-5
-
.
b.
A number of contaminated filters from the makeup system awaited processing and shipment. The licensee stated shipping arrangements
'
were being made.
The inspector noted that several new contaminated areas in the c.
auxiliary building had been established.
Health physics controls for these-areas appeared adequate to the inspector.
The inspector urged the licensee to consider steps, such as cleaning and painting during this outage, to minimize the effects of spilled contaminated liquids.
d.
The inspector identified several instances of peeling paint on nuclear services closed cycle cooling headers in the lower level reactor building.
The licensee has issued a non-conforming operations report (NCOR) and will evaluate this item.
The licensee acknowledged the inspector's comments concerning these housekeeping items.
8.
Review of Licensee Event Reports (LER's)
h)
\\
The inspector reviewed selected LER's for consistency with the
_,
requirements of the Technical Specifications and Regulatory Guide 1.16 (Reporting of Operating Information - Appendix A Technical Specifications). The inspector examined the licensee's analysis of the event, the corrective action taken, and discussed the LER with licensee representatives.
The following LER's were reviewed:
LER 77-156, Failure to Correctly Reduce NI Channel Overpower Setpoint a.
The inspector reviewed executed instrument calibration Data Sheets for December 12, 1977 and December 16, 1977, from SP-ll3,_.
Power Range Nuclear Instrumentation Calibration.
These data sheets related to this LER. Discussions with a licensee t
representative confirmed the designation of cause and corrective action taken.
This LER is closed.
b.
LER 77-159, Containment Isolation Valve AHV-1B Failed to Close The inspector reviewed this LER with the licensee and determined that there is no positive means to assure the containment i
isolation valve (for purge supply and exhaust) automatic
'
closure matrix is in the " ready" position when these valves are opened.
The licensee has recognized this design configuration and initiated REI PD-575 to rectify the problem identified in
[' \\
this LER. This LER remains open pending the issue and implementation N
of the system modification.
s
,
,
... -
,
, - -
-
,,.
-
____ _ __ _ __ _ ______-_ _____
- _ _ _ _ _ _ _ _ _ _ _ _ _ _
, ~%
O I
(x,)
_RII Rpt. No. 50-302/78-6 I-6
-
LER 78-001/03L, 3B Emergency Diesel Inoperable c.
'l The licensee has increased the oil sampling frequency for diesel-generator governor oil as a result of this and previous LER's related to diesel oil contamination.
This LER is closed.
d.
LER 78-002/03L, Cable Tunnel Sump Pump Inoperable The inspector confirmed the conduct of a pump qualification test subsequent to the installation of the replacement pump.
This LER is closed.
,
l l
e.
LER 78-004/03L, RCS High Dose Equivalent Iodine-131 The inspector confirmed log entries of events occurring as described in this LER. This LER is closed.
'
f.
LER 78-005/03L, Cable Tunnel Sump Pump Inoperable i
This LER was closed without comment.
g.
LER 78-006/03L, High Pressure Injection Valve MUV-25 Inoperable
-
This LER was reviewed in conjunction with conjunction with the
review of the licensee's corrective action taken in. response to Non-compliance Item 78-02-01 concerning Clearance Control.
This LER is closed.
h.
LER 78-011/03L, Containment Isolation Valve NGV-81 Left Open The licensee's corrective action is to station a man at manual containment isolation valves that are opened with the plant in the applicable operational mode.
This LER is closed, i.
LER 78-012/03L, Actuation of the "B" Steam Line Rupture Matrix The inspector stated that he would review the modification proposed as a result of this LER (78-06-04). This LER is closed.
j.
LER 78-013/03L, Borated Water Source Inoperable This LER is closed without comment.
-
J
.
-,
-
-,
-
.
I h
RII Rpt. No. 50-302/78-6 I-7 O
.
k.
LER 78-016/OlT, Unplanned Reactivity Insertion This LER was reviewed with the licensee based upon information e
available.to the NRC in the 24-hour report received by the inspector March 13.
The inspector reviewed operator logs of plant activities preceeding this event which occurred the morning of March 10.
It was determined that the root cause of i
this event was the failure to anticipate the affects of (possibly)
dilute boron concentrations in the RCS loops.
The licensee agreed that corrective action would address the root cause of
~
this event in the 14-day written submittal of this LER.
This LER remains open.
-
9.
In-Office Review of Licensee Event Reports (LERs)
The inspector reviewed various LER's for consistency with Technical Specification and Regulatory Guide 1.16 requirements. The LER's were examined to determine the cause of the event and the licensee's corrective action. The following LER's were reviewed and closed without comment in the NRC Regional Office:
f'~N LER Number Subject
,77-154 Failure to Log Control Rod Position Indication 77-155 Inoperable Engineered Safety Feature Actuation System Channel 77-158 3B Emergency Diesel Generator Inoperable 77-162 Failure to Test Containment Airlock 78-008/03L RCS Dose Equivalent I-131 High 78-009/03L Control Rod Drive ":aaker Failure 78-014/03L Containment Isolation Valves CAV 1&2 Inoperable 78-015/03L RCS Dose Equivalent I-131 High 10.
Review of IE Circulars and Bulletins The inspector reviewed applicable IE Circulars with licensee personnel to ascertain that they have been received on site and reviewed by cognizant supervisory personnel.
Licensee's actions on the following IE Circulars were reviewedt l
n-s_.
.
m -
60-e 4 e esee-emeee
,
- _ -...
-,
,
. - _.,, _, - - - - - - - _
.
_ _
l
.
.~.
f'y -i o/
RII Rpt. No. 50-302/78-6 I-8
1 Circular No.
Subject l
77-14 Separation of Contaminated Water Systems
.
From Non-Contaminated Plant Systems 77-15 Degradation of Fuel Oil Flow to Emergency Diesel Generator
_
l 77-16 Emergency Diesel Generator Electrical Trip Lock-out Features The inspector has no further questions on IE Circulars 77-14 and 77-16 since they have been received and reviewed by cognizant supervisory personnel. However, IE Circular 77-15 will remain open pending completion of the licensee's review.
The inspector reviewed applicable IE Bulletins with licensee personnel to ascertain; that they have been received by the licensee and reviewed for applicability by cognizant supervisory personnel; that information discussed in licensee's reply was accurate; and that corrective action taken was effected as described in the reply.
j The following IE Bulletins were reviewed:
~
Bulletin No.
Subject 77-08 Assurance of Safety and Safeguards During an Emergency-Locking Systems 78-01 Flammable Contact-Arm Retainers in l
G.E. CR120A Relays 78-02 Terminal Block Qualification
..
The inspector has no further questions on IE Bulletin 77-08, since documentation supporting the licensee's reply that this IE Bulletin
,
was not spplicable was available for inspection and was considered
'
satisfactory. However, IE Bulletins 78-01 and 78-02 will remain open pending an inspection at the Florida Power Corporate office.
.
l Documentation to support the replies to these Bulletins is retained I
.
at that location.
l v
i
-
,
,
-
,
,..
-.
.
_.
.
, _ -.
- _ _.
,
t
.
.
<s
,
b
'
'
RII Rpt. No. 50-302/78-6 I-9
.
11. Maintenance Administrative Controls The inspector reviewed the Crystal River 3 administrative controls
~
for maintenance. This review was with consideration for the FPC
response dated December 16, 1977, to the Item of Noncompliance concerning maintenance administrative controls issued December 2,
,
1977 (RII Report 50-302/77-21). The inspector reviewed the status of maintenance administrative controls, reviewed five recently generated safety-related maintenance packages and supporting documentation, and discussed his findings with licensee personnel.
Because various discrepancies (as described below) were identified in the inspector's review this noncompliance item remains open.
Revision to CP-113, Procedure For Handling nfscrepancies a.
and Corrective Actions
!
This procedure has not been revised.
The licensee plans to revise this procedure to reflect organizational changes, NRC comments concerning maintenance administration, and station policy changes relating to maintenance controls.
b.
Use of Clearances
-
'
The licensee is using clearances approved by the PRC to control plant manipulations for certain maintenance activities. This use is governed by Section 2.2.6.f of CP-115, in-Flant Equipment Clearance and Switching Orders.
The inspector identified the following discrepancies related to clearances used for maintenance:
CP-ll5 does not provide guidance concerning the scope of
-
a maintenance activity that may have plant manipulations controlled by the PRC-approved clearance (such as, minor maintenance activities involving a limited number of component manipulations and where existing operating or maintenance procedures are silent).
,
CP-ll5 does not provide criteria for determining when the
-
use of the PRC-pproved clearance would be unacceptable, and when complet* operation / maintenance procedures must be employed.
CP-115 is silent concerning " reuse" of a previously
-
approved clearance for repeat maintenance activities.
CP-115 is silent concerning deviations from a PRC-approved
-
clearance used in conjunction with a maintenance activity.
,
,
-
- r****dm*-#
.Q4f
'e
- e
- e-w e - e-e
+
- - - -
- - - -
- - - - + + - - - - - - -
+-ww
+
.
,
,-
,(Ni RII Rpt. No. 50-302/78-6 I-10 s_ /
.
c.
Review of Maintenance Packages The inspector noted that review of completed maintenance
-
packages by the maintenance supervisor occurs (in some instances)
several weeks after the completion of the maintenance.
Compliance section review may be several weeks following the supervisory review. The inspector also noted that supervisory review should identify.and correct discrepancies such as those described in item d, below.
d.
Inspector Comments Concerning 5pec!fic Maintenance Packages (1) WR-05907, RCV-8 Pressurizer Code 9afety Valve Maintenance, 2/1-2/2/78.
The work assignment section of the work request
-
was blank.
An error in the data sheet recording was identified
-
(although the maintenance was correctly executed).
(2) WR-06116, MU Filter 2A Change, 2/1/78
.
Portions of the applicable maintenance procedure
-
(MP-105, Filter Removal and Replacement) were omitted during the conduct of this maintenance.
No documentation concerning this omission was made on the Check Sheet or Work Request.
(3) WR-01118. Spent Fuel Pump SFP-1A Seal Welds On Vent, Seal Line, and Casing Drain, 10/20/77 The total time from completion of the maintenance
-
until completion of the package review and signoff was 4 1/2 months.
(4) WR-06226 Packing Leaks on RC Evaporator Vacuum Pumps WDP-21A&B, 2/21/78 This work request employed MP-121, Pump Repacking,
-
to govern the conduct of.the work.
Step 7.1 of MP-121 (which requires the use of a PRC-approved Clearance to isolate the affected equipment) was not followed.
O
.
.
.
.
-
_
.
.
.
.
.--._
___ _
.
-
,,
,
.
RII Rpt. No. 50-302/78-6 I-11
'
.
,
(5) WR-06148, Repair Hydraulic Cylinder on MSIV-412, 2/10/78 This maintenance involved three clearances for
-
manipulation of plant components.
Only ona of these
clearances had PRC approval.
The licensee acknowledged the inspectors comments and stated that they would be responsive.
,
.
I
..
i
l l
l
!
.
...
_ -.......... -..
.
.
.
,
._
_
__
. _ _
..
.