ML20151T303
| ML20151T303 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/05/1988 |
| From: | Orser W DETROIT EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-NUREG-0313, RTR-NUREG-313 GL-88-01, GL-88-1, NUDOCS 8808160311 | |
| Download: ML20151T303 (17) | |
Text
',,
e, 2"%t ~
nucw operew
,A, Detroit r-Edison meighway MM Nodn Dme H Nuclear August 5, 1988 NRC-88-0191 U. S. Nuclear Regulatory Commiscion Attn Document: Control Desk Wash.
'on, D. C.
20555
References:
1)
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43 1
2)
Detroit Edison Letter to NRC, "Response to Generic Letter 84-11", EF2-69,210, dated July 13, 1984 3)
Detroit Edison Letter to NRC, "Detroit Edison's Comments on the Draf t NUREG and Generic Letter regarding Intergranular Stress Corrosion Cracking (IGSLC)," VP-86-0129, dated September 19, 1986.
4)
NRC Generic Letter 88-01, "NRC Position on IGSCC In BWR Austenitic Stainless Steel Piping, dated Janua ry 25, 1988
Subject:
Response to NRC Generic Letter 88-01 l
Detroit Edison has reviewed the Generic Letter 88-01 (Reference 4) and the NUREG-0313 Revision 2.
In addition, measures to avoid or mitigate the effects of IGSCC at Fermi 2 have been re-evaluated to ensure that they do not rely entirely on an augmented ISI program for long term piping integrity and reliability.
Detroit Edison's response to each specific NRC item of Generic Letter 88-01 is provided in Enclosure 1. provides a list of welds by categories based upon the review of piping welds at Fermi 2.
.to y. _ -i) #
'I
^
$ 001 lSP*$8SM !s888sy
//j PDC
___,__---__,_-------.w----------------
h a
e i
i 1
l 1
Cl: I& 6-my gg, 1
E01'10llv1no3y YJa Hv J 3 n's n. n a n y
USNRC August 5, 1988 NRC-88-0191 Page 2 If-you;have any furthet-questions, please contact Mr. Girija ~ Shukla at (313) 586-4270.
Sincerely, i
Enclosures cca Mr. A. B. Davis Mr. R. C. Knop Mr. T. R. Quay Mr. W. G. Rogers s
mi-m.
l l
j 1
USNRC l
August 5, 1988 i.
Page 3 I WILLIAM S. ORSER, do hereby af firm that the foregoing statements are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.
ll WILLTAM S. OYSER Vice President hbclear Operations On this 8%I/
day of
//Xg(Zw'[ 1988, before me personally appeared William S. Orserg/being first duly sworn and says thst he executed the foregoing as his free act and deed.
i i
htl
.kfL.()&
N Nota ry P' lic L CNUON NaNwy Putsc.% Counh, Mi MyComnesionaseenJon,as,1991 j
1
+
NRC-88-0191 Page 1-Response to Specific iRC Items Guneric Letter 88 The Detroit Edison response to each NRC item of the Generic Letter 88-01 is given below:
NRC I t em No. 1 Current Fermi 2 plans regarding pipe replacement and/or other measures taken or to be taken to mitigate IGSCC and provide ascurance of continued long-term piping integrity and reliability.
Response
Fermi 2 is a relatively new plant currently operating in its first fuel cycle. As such no IGSCC problem has been found at Fermi 2 and the potential for IGSCC existing at this time is very small.
Therefore, no current plans are being made for replacing pipe due to cracking problems. Based on the extensive mitigation actions taken no plans are being made to replace piping.
In response to Generic Letter 88-01, a review.was completed of all Fermi 2 piping which meets the following criteria:
1.
Piping made of austenitic stainless steel, 2.
Four (4) inch or larger diameter, i
3.
Contains reagtor coolant.
4.
Is above 200 F during normal power operation, and 5.
Regardless of code classification.
In addition the reactor vessel attachments and appurtenances were reviewed for applicability.
This review han located some components that may be susceptible to IGSCC. From these I
components, 27 welds have been identified under NJREG-0313, l
Revision 2 criteria for IGSCC susceptible welds. This represents only 18% of the total population of 144 welds within the scope of Generic Letter 88-01.
These category "G" welds are listed in The IGSCC susceptible components are all associated with the Recirculation System except for the capped hydraulic j
return nozzle, core spray safe end welds, jet pump safe end assembly welds, and two dissimilar velds in the Reactor Water Cleanup System.
Detroit Edison has taken many steps to avoid IGSCC at Ferei 2.
Among these are the replacement and heat treating of pipe and 1
-Enclosure 1 NRC-88-0191 Page 2 components before operation. A summary of these actions is provided heret o
Reactor Pressure Vessel (RPV) safe ends were wcld buttered and solution annealed prior to welding to the RPV nozzles.
Welding the safe ends to the RPV nozzles occurred.af ter finci post weld heat treatment of the RPV.
o Recirculation loop piping was purchased by the pipe fabricator in the solution annealed condition.
The bypass line around the recirculation pump discharge o
isolation valve was removed. These sweepolets were then capped with 308L weld buttered caps.
Core spray stainless steel safo ends and piping were o
replaced.
Safe end is now inconel and the piping is carbon
- steel, o
Control Rod Drive (CRD) return line was removed.
Nozzle safe end removed and a cap welded to the RFV nozzle weld buttering.
o Recirculation Loop Riser Piping was modified to add corrosion reristant veld buildups on each field weld end and each spool solution annealed after fabrication.
o After field erection and before operation 79 welds in the recirculation loop piping were given an Induction Heating Stress Improvement (IHSI) heat treatment.
(NOTE: Of 144 potentially susceptible welds, 117 have received either a solution annealing or IHSI heat treatmont before operation.)
During field erection ferrite limits were imposed on filler o
metals and heat input during welding was carefully controlled. Also controlled was grinding of piping inside
- surfaces, The CRD System was modified to provide a source of low o
oxygenated water, (Condensate Demineralizer Effluent).
At this time no further modifications are planned for piping or components. Ef forts for short and long term reliability are ceatered on water chemistry control, an augmented ISI program, and evaluation of applicable stress improvement processes,
)
NRC-88-0191 Page 3 particularly the Mechenical Stress Improved Process (MSIP). The water chemistry controls are explained in the following paragraphs and the ISI program is discussed in the response to the NRC Item No. 2.
Based on preliminary investigation the MSIP process may be suitable for a majority of the non-mitigated welds identified in.
Investigation of this or other processes will continue through the first fuel cycle. Prior to the first refueling outage a decision will be made on a possible method for mitigation of IGSCC susceptibility in welds and a stress improvement process will be selected, if appropriate.
Currently the Fermi 2 Water Chemistry Specifications meet or exceed the intent of the BWR Owners Group Guidelines for mitigation of IGSCC in the primary coolant. Measures have been taken to reduce sulfate action icvels in the reactor coolant.
Fermi 2 plans tc implement Hydrogen Water Chemistry pending evaluation of a mini-test. Current plans are to perform the mini-test by the first refueling outage.
NRC Item No. 2 An Inservice Inspection (ISI) Program to be implemented at the refueling outage for austenitic stainless steel piping next covered under the scope of the Generic Letter that conforms to the staf f positions on inspection schedules, methods and personnel, and sample expansion included in the Generic Letter.
Response
Piping welds at Fermi 2 have been reviewed to determine the applicable category as defined by NUREG 0313 Revision 2, and the Generic Letter 88-01.
Welds have been divided into Categories A, B and G.
identifies the weldt included in each category. As recommended, a minimum of 25% of the Category "A" welds, 50% of the Category "B" welds and all Category "G" welds will be inspected as directed within the first ten year (120 Honth) inspection cyzle.
All Category "G" welds will be inspected at the first refueltug outage at which time the velds will be upgraded to Category GD".
Detroit Edison performed IMSI to 79 velds prior to plant operation in July 1983.
Selected welds were reinspected in accordance with proposed Code Case N-333.
This was sufficient i
1 W
NRC-88-0191 Page 4 and acceptable for a new plant as discussed in Reference 2.
Therefore, all welds treated by IHSI have been considered as Category "B".
The current IFI contractor for Fermi 2 has personnel qualified to the requirements of IE Bulletin 83-02 and EPRI guidelines as-upgraded in September 1985. All futuro contracts for NDE at Fermi 2 will require that examination procedures, equipment and examiners for austenitic stainless steel welds be qualified by demonstration in accordance with current EPRI guidelines.
The Fermi 2 ISI/NDE Program plan will be revised to include the additional welds and will be implemented by the first refueling outage.
NRC Item No. 3 A change to the Technical Specifications to include a statement In the section on ISI that the Inservice Inspection Program for piping covered by the secpe of the Gederic Letter will be in i
conformance with the staff positions on schedule, methods and personnel, and sample expansion' included in the Generic Letter (see enclosed model BWR Standard Technical Specification).
It is i
recognized that the Inservice Inspection and Testing sections may be removed from the Technical Specifications in the future in line with the Technical Specifications Improvement programs.
In this case, this requirement shall remain with the ISI section when it is included in an alternative document.
Responses The proposed change to Fermi 2 Technical Specifications will be subaitted by December 31, 1988.
NRC It em No. 4 Confirmatien of your plans to ensure that'the Technical Specification related to leakage detection will be in conformance with the staff pcsition on leak detection included in this letter.
ll l
NRC-88-0191 Page 5
Response
Detroit Edison has reviewed the "Staff Position on Leak Detection" contained in Generic Letter 88-01.
As the result of our review we have concluded that the Fermi Reactor Coolant System Leakage Detection System is in conformance with Position C of Regulatory Guide 1.45.
The Staff had previously accepted the Fermi leak detection design as evidenced by Section 5.2.5 of NUREG-0798.
Fermi employs a leak detection system which incorporates three distinct methods of monitoring reactor coolant Icakage. They are:
a.
Primary containment sump flow monitoring system which consists of both drywell equipment and floot drain sump icvel and flow monitoring to determine both identified and unidentified leakage rates respectively, b.
Airborno nobic gas radioactivity monitoring for diversity of detection means.
c.
An independent floor drain sump level monitor which provides the required Icak detection sensitivity and seismic withstand capability. This monitor has been accepted by the Staf f as an alternative for the previously required airborne particulste monitor.
Fermi Technical Specifications for reactor coolant system leaktge require shutdcwn within a 24-hour period if either the total unidentified leakage exceeds 5 spm or the increase in the rate of leakage exceeds 2 gpm in a four hour period.
These Specifications are in agreement with the Staff Position. The drywell floor drain icvel measurement system is monitored continuously and the calculation of leak rate is performed at a frequency such that a lesk rate increase of 1 gpm in one hour can be detected.
Unidentified leakage within the drywell is directed toward and collected solely within the floor drain sump.
Thus, variation of the sump level can be used to account for all leakage except that which is contained in the drywell atmosphere.
Hence, the sump level is used as the primary indication of leakage and is monitored directly for change by two independent systems, the level / flow monitor and the sump level monitor. The noble gas activity monitor indirectly monitors unidentified leakage.
~ -
NRC-88-0191 Page 6 Fermi has IGSCC susceptible welds which are Category G welds, as a result the Staff positien requires that at least one of the leakage measurement instruments associated with each sump shall be operable and the outage time for inoperable instruments.to be limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or initiate an orderly shutdown.
l The Fermi Technical Specification 3.4.4.3 complies with this t
staff position provision based on the fact that either the primary containment sump flow monitoring system or the drywell floor drain sump level monitoring system is cequired to be operable or the plant must be in hot shutdown within 12-hours and-f cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Either sump level monitor can be out-of-service for thirty days, but if both direct sump monitors are out-of-service, the Plant must be in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This specification is interpreted by Detroit Edison to meet the Staff guidance in that the sump is not allowed to be unmonitored for a period exceeding 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> without being in hot shutdown.
NRC Item No. 5 t
l In accordance with 100FR50.55a(o), the plans to notify the NRC of any flaws identified that do not meet IWB-3500 criteria of Section XI of the Code for continued operation without evaluation, or a change found in the condition of the welds previously known to be cracked, and your evaluation of the flaws for continued operation and/or your repair plans.
Response
)
l Notification of any flaws would be accomplished thru our normal j
deficiency reporting process and our ISI program reporting.
1 Specifically the Fermi 2 Deviation Event Reporting (DER) process requires a DER be written for ISI found flaws. These are subject to an internal review and a reportability requirement is included. Also, the ISI process furnishes a formal report which is submitted within 90 days of completion of the outage in which the examinations were completed (
Reference:
ASME Section XI Subsubarticle IWA-6230).
l
NRC-88-0191 Page 1 LIST OF WEIDS BY CATEGORY CATEGORY "A"
9 ELDS Solution Post IHSI Weld Number IHSI Annealed UT Inspection Remarks SW-RS-2-A3-W3 X
28" Pipe - SWOL SW-RS-2-A3-W2 X
28" Pipe - SWOL SW-RS-2-A3-W1 X
28" Pipe - Elbow SW-RD-2-Al-W1 X
28" Pipe - SWOL SW-RD-2-A2-W3 X
28" Pipe - SWOL SW-RD-2-A3-W1 X
22" Pipe - SWOL SW-RD-2-A3-W2 X
22" Pipe - SWOL SW-RD-2-A3-W3 X
22" Pipe - SWOL SW-RD-2-A3-W4 X
22" Pipe - SWOL SW-RD-2-A7-W1 X
12" Pipe - Elbow SW-RD-2-A7-W2 X
12" Elbow - Pipe SW-RD-2-A6-W1 X
12" Pipe - Elbow SW-RD-2-A6-W2 X
12" Elbow - Pipe SW-RD-2-A8-W1 X
12" Pipe - Elbow SW-RD-2-A8-W2 X
12" Elbow - Pipe SW-RD-2-A5-W1 X
12" Pipe - Elbow SW-RD-2-A5-W2 X
12" Elbow - Pipe SW-RD-2-A4-k1 X
12" Pipe - Elbow SW-RD-2-A4-Wi X
12" Elbow - Pipe SW-RS-2-B3-W3 X
28" Pipe - SWOL SW-RS-2-B3-W2 X
28" Pipe - SWOL SW-RS-2-B3-W1 X
28" Pipe - Elbow SW-RD-2-B1-W?
I 28" Pipe - SWOL SW-RD-2-B2-W3 X
28" Pipe - SWOL SW-RD-2-B3-iti X
28" Pipe - SWOL SW-RD-2-B3-W2 X
22" Pipe - SWOL SW-RD-2-B3-W3 X
22" Pipe - SWOL SW-RD-2-B3-W4 X
22" Pipe - SWOL i
SW-RD-2-B7-W1 X
12" Pipe - Elbow SW-RD-2 -B7-W2 X
12" Elbow - Pipe SW-RD-2-B6-W1 X
12" Pipe - Elbow SW-RD-2-B6-W2 X
12" Elbow - Pipe SW-RD-2-B8-W1 X
12" Pipe - Elbow SW-RD-2-B8-W2 X
12" Elbow - Pipe SW-RD-2-B5-W1 X
12" Pipe - Elbow SW-RD-2-B5-W2 X
12" Elbow - Pipe SW-RD-2-B4-W1 X
12" Pipe - Elbow SW-RD-2-B4-W2 X
12" Elbow - Pipe j
i i
NRC-88-0191 Page 2 CATEGORY "B"
WELDS Solution Post INSI (1)
Weld Number IHSI Annealed UT Inspection Rema rks FW-RS-2-Al X (1)
X 28" SE - Pipe SW-RS-2-Al-W1 X (2)
X 28" Pipe - Elbow SW-RS-2-Al-W2 X (3)
X 28" Elbow - Pipe FW-RS-2-A2 X (4) 28" Pipe -. Pipe SW-RS-2-A2-W2 X (5) 28" Pipe - Pipe SW-RS-2-A2-W1 X (6)
X 28" Pipe - Elbow i
FW-RS-2-A3 X (7)
X 28" Elbow - Valve FW-RS-2-A4 X (8) 28" Valve - Pipe SW-RS-2-A3-W4 X (10) 4" SWOL - Pipe SW-RS-2-A3-W5
% (11) 4" Pipe - Flange FW-RS-2-A5 X (17)
X 28" Elbow - Pipe FW-E11-2298-6WC X (66)
X 24" Pipe - Pipe RHR/
LPCI FW-E11-2298-6WO X (65)
X 24" Pipe - Tee RHR/
LPCI FW-G33-3096-12WF3 X (13)
X 4" SWOL - Tee RWCU FW-G33-3096-12WF2 X (14) 4" Tee - Reducer RWCU FW-G33-3096-12WF1 X (15)
X 4" Tee - Pipe RWCU FW-RD-2-A6 X (18)
X Pump - 28" Pipe FW-RD-2-Al-W1 X (20)
X 4" SWOL - Cap FW-RD-2-A7 X (21) 28" Pipe - Valve FW-RD-2-A8 I (22) 28" Valve - Pipe SW-RD-2-A2-W1 X (23) 28" Elbow - Pipe FW-RD-2-A2-W2 X (25)
X 4" SWOL - Cap FW-RD-2-A9 X (29)
X 28" Tee - Cross SW-RD-2-A3-W5 X (43) 28" Cross - Reducer SW-RD-2-A3-W6 I (49)
Cross - 22" Pipe SW-RD A3-W7 X (31)
X Cross - 22" Pipe SW-RD-2-A3-W9 (cap) X (42)
X 22" Pipe - Cap SW-RD-2-A3-W8 (cap) X (60)
X 22" Pipe - Cap FW-RD-2-A14 X (56)
X (EB) 12" SWOL - Pipe FW-RD-2-A19 X (57)
X (EB) 12" Pipe - SE FW-RD-2-A13 X (51)
X (EB) 12" SWOL - Pipe FW-RD-2-A18 X (54)
X (EB) 12" Pipe - SE FW-RD-2-A12 7 (44)
X (EB) 12" Reducer - Pipe FW-RD A17 X (47)
X (EB) 12" Pipe - SE j
FW-RD-2-A11 X (33)
X (EB) 12" SWOL - Pipe FW-RD-2-A16 X (36)
X (EB)
X 12" Pipe - SE FW-RD-2-A10 X (38)
X (EB) 12" SWOL - Pipe j
FW-RD-2-A15 I (41)
X (EB) 12" Pipe - SE FW-RS-2-B1 X (1) 28" SE - Pipe SW-RS-2-B1-W1 X (2) 28" Pipe - Elbow SW-RS-2-B1-W2 X (3) 28" Elbow - Pipe FW-RS-2-B2 X (4) 28" Pipe - Pipe SW-RS-2-B2-W2 X (61) 28" Pipe - Tee I
NRC-88-0191 Page 3
,C A T E G O R Y "B"
W E L D S (Continued)
Solution Post IHSI (1)
Weld Number IHSI Annealed UT Inspection Rema rks SW-RS-2-B2-W10A X (5) 28" Tee - Pipe SW-RS-2-B2-W1 X (6) 28" Pipe - Elbow FW-RS-2-B3 X (7) 28" Elbow - Velve FW-RS-2-B4 X (8) 28" Valve - Pipe SW-RS-2-B3-W4 X (10) 4" SWOL - Pipe SW-RS-2-B3-W5 X (11) 4" Pipe - Flange FW-RS-2-B5 X (17) 28" Elbow - Pump SW-E11-2299-1WB X (64)
X 20" Pipe - Pipe RHR/SDC DM (2)
FW-E11-2299-0WI X (63)
X 20" Pipe - Tee RHR/SDC LM (2)
SW-E11-2327-6WC X (66)
X 24" Pipe - Pipe RHR/LPCI DM (2)
FW-E11-2327-6WO X (65)
X 24" Pipe - Tec RHR/LPCI DM (2)
FW-G33-3096-10WF2 X (14) 4" Tee - Reducer RWCU FW-G33-3096-10WY3 X (13) 4" SWOL - Tec RWCU FW-G33-3096-10WF1 X (15) 4" Tee - Pipe RWCU FW-RD-2-B6 X (48) 28" Pump - Pipe FW-RD B1-W1 X (20) 4" SWOL - Cap FW-RD-2-B7 X (21) 28" Pipe - Valve FW-RD-2-58 X (22) 28" Valve - Elbow SW-RD-2-B2-W1 X (23) 28" Elbow - Pipe FW-RD-2-B2-W2 X (25) 4" SWOL - Cap FW-RD-2-B9 X (29) 28" Tee - Cross SW-RD-2-B3-W5 X (43) 28" Cross - Reducer SW-RD-2-B3-W6 X (49)
Cross - 22" Pipe SW-RD-2-B3 -W7 X (31)
Cross - 22" Pipe SW-RD-2-B3-W8 (cap) X ' 0) 22" Pipe - Cap SW-RD-2-B3-W9 (cap) X 42) 22" Pipe - Cap FW-RD-2-B14 X (56)
X (EB) 12" SWOL - Pipe FW-RD-2-B19 I (59)
X (EB) 12" Pipe - SE FW-RD-2-B13 X (51)
X (EB) 12" SWOL - Pipe FW-RD-2-B18 X (54)
X (EB) 12" Pipe - SE FW-RD-2-B12 I (44)
X (EB) 12" Reducer - Pipe FW-RD-2-B17 X (47)
X (EB) 12" Pipe - SE FW-RD-2-B11 X (33)
X (EB) 12" SWOL - Pipe FW-RD-2-B16 X (36)
X (EB) 12" Pipe - SE FW-RD-2-B10 X (38)
X (EB) 12" SWOL - Pipe FW-RD-2-B15 X (41)
X (EB) 12" Pipe - SE
NRC-88-0191 Page 4 C A T E G_O R Y "G"
W E L D__S Solution Post IHSI Weld Number INSI
!.nnealed UT Inspection Remarks SW-G33-3096-12WD 4' Pipe - Pipe RWCU DM (2)
SW-RD-2-A2-W20 28" Pipe - Pipe SW-RD-2-A2-W2 28" Pipe - Pipe SW-G33-3096-10WD 4" Pipe - Pipe RWCU DM (2)
SW-RD-2-B2-W20 28" Pipe - Pipe SW-RD-2-B2-W2 28" Pipe - Pipe 4-303A 28" SE-Nozzle (3) 4-303B 28" SE-Nozzle (3) 2-303A 12" SE-Nozzle (3) 2-303B 12" SE-Nozzle (3) 2-303C 12" SE-Nozzle (3) 2-303D 12" SE-Nozzle (3) 101-304E 12" SE-Nczzle (3) 2-303P 12" SE-Nozzle (3) 2-303G 12" SE-Nozzle (3) 2-303H 12" SE-Nozzle (3) 2-303J 12" SE-Nozzle (3) 2-303K 12" SE-Nozzle (3) 102-304A Jet Pump 2nstrumenta-tien SE-Nozzle (3) 102-304B Jet Pump Instrumenta-tion SE-Nozzle (3)
NCA Jet Pump Instrumenta-tion SE-Seal Assesbly (4)
N8B Jet Pump Instrumenta-tion SE-Seal Assembly (4)
NSA Core Spray SE-Nozzle NSB Core Spray SE-Nozzle SW-E21-3052-4WOX Core Spray SE-SE Ext.
(5)
SW-E21-3053-4WOX Core Sptay SE-SE Ext.
(5)
N9 CRD Hydraulic Return Nozzle Cap
NRC-88-0191 Page 5 i
Notes:
(1)
Welds identified with an asterisk (*) are c?assified as Category "B" welds since IHSI was performed prior to plant operation with a representative sample reinspected per Code Case N333.
(2)
(3)
SE - Nozzle:
(4)
SE - Seal Assembly:
Safe End to Seal Assembly.
(5)
Safe End to Safe End Ext. (INCO 600 - CS)
V6 Tc^.
-1208775 REOULAT0RY INF0RMATION TRACKINo SYSTEM PAGE 3
,4, MRR STAFF INPUT REPORT OFFICE: NRR DIVISIDH DONR A/D PERIOD ENDING 08/.AGr88 MPLOYEE - (GTM) - G MCPHERSON ORGANIZATION: DONR RUN DATE 08/0,8/88 PLA #
il 0 U R S CODE RgpMLAR NON-REG DESC JNK GENERAL CORRESPONDENCE B00 STAFF DEVELOPMENT & PROFESSIONAL MEETINGS C00 GENERAL TRAVEL TCS M._
1._
TECHNICAL C00RDINATION & SUPPORT d._
ABSENCE (EXCLUDING LHOP)
H00 CERTIFY TNAT, TO THE BEST OF MY KNOHLEDGE, T ~ l ALLOCAT ONS REPORTED ON THIS FORM ARE ACCURATE.
EMPLOYEE'S SIGNATURE & DATE
/
E b
.6 I
9tEDIATE SUPERVISOR'S SIGNATURE & DATE:
1
)
$ w f S ( f " y. 'N y,~ 7
/
(
l
~
I
-1208775 REOULAT0RY I N F 0 R H A T I O fl TCACKING SYSTEM PAGE 4
!!iRR STAFF INPUT INSPECTI0ft REPORT OFFICE: NRR DIVISI0ft: DONR A/D:
HEEK ENDING 08/13/83 l
NPLOYEE - (GTM) - G MCPHERSON BRANCH: D0f3R SECTION:
RUll DATE 08/08/88 BC CCDE - 10 NSPECTION ACTIVITIES DOCKET NUMBER I
l l
IfiSPECTION REPORT fiUMBER l
l l
l l
IMI CODE l
l l
1 ACTIVITY HOURS 1
HOURS l
HOURS l
HOURS l
HOURS l
fiOff 0 N0!I O fl0!I O l NON 0 i NON O I DESCRIPTION NUM.
REG REG T REG REG T REG REG T REG REG T l REG REG T I
-_---g-_-
I I
I I
OUTI!1E PREVENTIVE PREPARATION IM3 APP l
i l
1 OUTI!1E PREVENTIVE INSPECTION lM3 API l
l l
OUTINE PREVENTIVE DOCUMEllT.
M3APD l
l l
1 l
l lEACTIVE PREPARATION M3ARP l
l l
'EACTIVE IfiSPECTION l M3ARI l
l l
l EACTIVE DOCUMEllTATIO!!
M3ARD l
il 1
i l
l l
HDEPET ENT PREPARATI0ft IM3AIP l
l l
NDEPENDENT IllSPECTION M3AII l
l l
PIDEPENDENT DOCUMENTATION M3 AID l
l l
l l
l SP0f4SE TO EVENTS / INCIDENTS IM3BD2,
l l
I l
ORMAL ENFORCEMENT ACTIVITIES M3BA1 l
l
$CALATED ENFORCEMENT lM3EA2 ll l
l l
I I
I I
I NSPECTION-RELATED TRAVEL M3AT l
l l
l l
l l
l
.LEGAT70N FOLLOH-UP (INSP) 183BJ1 l
l l
_LEGATI0f4 FOLLOH-UP (PREP / DOC)l83BJ2 l
l l
,_ 1 I
l l
l l
1 1
I, ITEMS OF MAJOR INTEREST (IMI CODES)
IPAT - PAT IflSPECTIONS l
ISSI - SSFI/SSOMI I!3SPECTIONS l
IVEN - VENDOR IIISPECTION l
ISPI - SPECIALIZED INSPECTIONS l
l IITI - INCIDENT INVESTIGATION TEAM l
l IDEA - DIAGfl0STIC EVALUATIONS I
I IORT - OPER READINESS TEAM INSPECTION I
i 10ST - OPERATIONAL SAFETY TEAM I!3SPECTIONS l DTE:
I IMTI - MAIllTENANCE TEAM INSPECTION l
NSPECTION REPORT NUMBER REQUIRED FOR ALL l l
NOTE:
NTRIES: IF NOT APPLICABLE, EllTER "N0llE" l
I M DOCKET AND IMI REQUIRED ti THE LEPORT NUMBER FIELD l
8 DOCKET NUMBER REQUIRED l