ML20137K822
| ML20137K822 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 09/03/1996 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17354B293 | List:
|
| References | |
| FOIA-96-485 JPN-PSL-SEES-96, NUDOCS 9704070107 | |
| Download: ML20137K822 (79) | |
Text
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- t FLORIDA POWER & LIGHT COMPANY l i 1 i
EVALUATION OF TEMPORARY OPERATING CONFIGURATION i WITH 1B MAIN TRANSFORMER OUT OF SERVICE i . l t
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,i - i ST. LUCIE NUCLEAR PLANT i i t : UNIT 1 , i e i i i !
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- REVISION 0 i s
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4 . i k a 9704070107 970325 ' PDR FOIA BINDER 96-405 PDR
s JPN-PSL-SEES-96-068
, REVISION O PAGE 2 OF 9
, TABLE OF CONTERTS i' 4 SECTION IJJL, pjrg Cover 1 { 1 Table of Contents 2 Review and Approval 3 j 1.0 Purpose / Scope 4 2.0 Background 4 3.0 Design Basis 4 4.0 Evaluation 5 5.0 Conclusion 7 j 6.0 Verification Summary 7 4 4 7.0 Plant Restriction 7 4 8.0 Implementation 7 9.0 References 9 4 ATTACHMENTS 1 1 Protective Relaying Changes. Rev. 0 5 pages ) 2 Isophase Enclosure Duct Plug Detail 2 pages i i
JPN-PSL SEES-96-068 REVISION 0 PAGE 3 0F 9 REVIEW AND APPROVAL RECORD l PLANT ST. LUCIE UNIT 1 TITLE EVALUATION OF TEMPORARY OPERATING CONFIGURATION. AS A RE1 TRANSFORMER FAILURE 1 l l LEAD DISCIPLINE ELECTRICAL ENGINEERING ORGANIZATION ST. LUCIE ENGINEERING GROUP REVIEW / APPROVAL: INTERFACE TYPE GROUP PREPARED VERIFIED APPROVED INPUT REVIEW N/A FPL APPROVED
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OTHER INTERFACES ' ' " DATE: 9/S/% NONE Corm 24, 9ev *1 N 1
JPN-PSL SEES 96-068 REVISION 0 PAGE 4 0F 9 1.0 PURPOSE / SCOPE This evaluation provides for the temporary operating configuration using only Main Transformer 1A until repair and testing of the Main Transformer 1B cooling system is satisfactorily completed and the transformer can be returned to service. 2.0 n E KGROUND In response to IB Hain Transformer gas detection alarm it was discovered that air is being introduced into the transformer oil.- PSL Unit I normally operates with the 1A and IB main transformers in parallel. However, system design allows for operation with a single main transformer provided certain conditions are itet. This evaluation focuses on the required configuration related to operation of the Unit utilizing only Main Transformer 1A. 3.0 DESIGN BASIS The station main generator is a 1000 MVA Westinghouse generator which provides pt. war to the offsite transmission network at various loads to a maximum of 850 MWe, The main generator data are given by Table 8.2-1. The main generator is direct connected through a 22 kv 28.000 ampere isolated phase bus to the main transformers, where it is stepped up to 240 kv and then tied to one bay of the outdoor switchyard. The main transformer bank consists of two (2). tliree-phase transformers 475 MVA each, forced oil and air (F0A) cooled at 65'C tenperature rise, connected in parallel. with separate cooling equipment such that any one transformer can be uprated to 632 HVA at 65'C , rise if the other transformer is out of service and all the cooling equipment is applied to the remaining transformer. The generator isolated phase bus is forced air cooled and is rated for both nonnal (two main transformers in service) and emergency operation (one main transformer out. the other uprated to 632 Mva) all at 65'C rise. Two 100 percent capacity sets of cooling equipment are provided. The ' Transformer Deluge system is mentioned in section 9.5.3.1.3, 9.5.3.3 and TABLE 9.5A-3. This system is for fire suppression of the Main Transformers.
. - . --- - - . - - - ... ~ . . - . - - - . - - - - - -
c ; JPN PSL SEES-96-068 i 4 REVISION 0 l PAGE5OF9 . l Technical Soecifications - AC Power Sources T.S. 3.8.1.1 - As a minimum, the following A.C. electrical power sources shall be } OPERABLE (Ref 3): j
- a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system. and 4
$ b. Two separate and independent diesel generator sets each with, etc. .... I This technical specification is applicable in modes 1. 2. 3. and 4. Disabling Main Transformer IB does not adversely impact operability of AC power sources as described l in technical specification 3.8.1.1. Operation of the Unit in the temporary alignment. ! utilizing only Main Transformer 1A. does not adversely impact operability of the AC power sources, since the startup transformers are unaffected by this alignment. Two j physically independent circuits between the offsite transmission network and the onsite
- Class 1E distribution system and the two diesel generator sets are maintained operable l in the proposed alignment.
i i Likewise. T.S. 3.8.1.2 - A.C. power sources, applicable in modes 5 and 6. are i unaffected by operation of the Unit in the proposed alignment utilizing Maia l Transformer 1A.
- The main transformers, main generator and the isophase bus are non safety related
- equipment and do not interact with any safety related structure, system, or component.
The deluge system is quality related. This engineering evaluation is therefore. I classified as Quality Nuclear Safety. 4.0 EVALUATION P , Alternate Alianment usino Oniv Main Transformer 1A 4 ! The temporary alignment utilizes a single transformer Main Transformer 1A. instead cf ! the normal configuration of two main transformers in parallel. Operation with a single ! main transformer is described in the Unit 1 FSAR uprated to 632 MVA at 65'C rise if tne I other transformer is out of service and all the cooling equipment is applied to the l remaining transformer. Since the cooling equipment from the IB transformer is not available the transformer will be used at its nominal rating of 475 MVA. 1 l
- The 65'C rise limit for the transformer is measured over the ambient cooling air i temperature. The cooling air temperature shall not er.ceed 40*C and the average i temperature of the cooling air for any 24 hour period shall not exceed 30*C.
4 i
JPN-PSL-SEES 96-068
' REVISION 0 PAGE 6 0F 9 As the 1A and IB main transformers share a comon fire detection and deluge system. '
1 fire protection for the 1A transformer will be affected during the 18 transformer work , activities. Normal compensatory measures shall be taken as provided for by the St. ! Lucie Unit 1 Fire Protection Program. 4 The fire water supply tb the IB main transformer will be capped to allow auto initiation of the 1A main transformer deluge system. While the IB transformer is out of service its most significant ignition source will be unavailable, minimizing the ( need for fire suppression system on the IB Main Transformer. Fire suppression is still i available for the 1A transformer. !
, 10 CFR 50.59 Screenina The answers to the following 10CFR50.59 screening questions demonstrate that che temporary alignment utilizing Main Transformer 18 does not require a 10CFR50.59 evaluation. '
- 1. Does the alternate alignment represent a change to the facility as described i in the SAR? ,
1 ( No. the activity' evaluated involves an alternate electrical lineup in which a single main transformer is operated as described in FSAR Section 8.2.1.4. i 2. Does the alternate alignment represent a change to procedures as described l in the SAR? No. there are no procedures described in the Unit 1 FSAR that would be impacted by this alternate alignment.
- 3. Is the alternate alignment associated with a test or experiment not descrilied in the SAR?
No, the proposed activity is not a test or experiment. The temporary ; alignment utilizing a single main transformer as described in FSAR Sect;on 8.2.1.4. { l
- 4. Could the alternate alignment affect safety in a way not previously evaluated 4
in the SAR?
. i No, the proposed activity represents an electrical alignment that was previously evaluated in the FSAR.
- 5. Does the alternate alignment require a change to Technical Specifications?
No. the proposed activity does not adversely impact any technic.al specification nor does it require a change to technical specifications.
l 4 JPN PSL SEES 96-068
- REVISION 0 PAGE 7 0F 9 i l
5.0 CONCLUSION
l I The temporary alignment utilizing Main Transformer 1A is part of the design basis v. the plant documented in the FSAR and determined to be acceptable. Further, the design l basis for the onsite and offsite electrical transmission, as described in the FSAR and j technical specifications. is judged not to be compromised. Therefore, the operation I and safety of St. Lucie Unit 1 is not adversely affected and operation is acceptable , utilizing Main Transformer 1A. ~ 1 ! 6.0 VERIFICATION
SUMMARY
The scope of this verification was to review the inputs and references to determine if the conclusions were reasonable in comparison to the inputs and references. The method used for this verification consisted of ensuring that the. applicable references, coces
- and standards, and regulatory requirements were addressed and properly reflected in tne j evaluation. The verifier concurs with the Quality Related Safety classification of this evaluation.
7.0 PLANT RESTRICTION , With the alternate alignment, the main transformer loading shall not exceed 475 MVA and/or temperature rise for the main transformer shall not exceed 65'C over the ambient cooling air temperature. The cooling air temperature shall not exceed 40*C and the average temperature of the cooling air for any 24 hour period shall not exceed 30*C. i 1 8.0 IMPLEMENTATION j Alternate Alignment Requirements i , 1. Isolated Phase Bus The bus was designed to operate with one of the main transformers out of service i as shown on EMDRAC Drawings 8770-1199. Rev. 5 and 8770-1200 Rev. 3. Tht:se ratings are, with forced cooling operable. 28.000 A for the main bus,18.500 A l (705 HVA) for the main transformer bus (with one transformer in service) and 2500 A (Self cooled rating) for the auxiliary transformer and potential transformer taps. Forced cooling air shall be available to the isophase bus duct for the
, operational transformer only. This will require installation of devices, such ,
as end caps where the bus has been disconnected (See Attachment 2).
FN-PSL SEES-96-068 REVISION 0 PAGE 8 0F 9
- 2. Main Transformer Each of the main transformers is rated 475 MVA with a guaranteed average winding temperature rise of 65'C. The design rated operating temperature is 86 C for insulating oil. Alarms are provided for a top oil temperature (set at 90'C) and for the hot spot winding temperature (120'C). Operation of transformers at ;
higher than design temperatures results in a loss of life of the insulation l system, with a potential for a transformer failure. This loss of life is proportional to the temperature and time. To prevent unnecessary alarms l annunciator switches will be turned off in accordance with attachment 1 (marked I up copies 8770-B-327 sheets 864 and 899). l The fire water supply to the IB main transformer will be capped to allow auto initiation of the 1A main transformer deluge system. Observe applicable fire protection plant procedures and compensatory measures. Insulating oil cross tie valves between the 1A and IB Main Transformers must be closed and locked in the closed position during the repair activities. Standard FPL isolating and grounding procedures shall be followed.
- 3. Protective Relaying Protective relaying dedicated solely to Main Transformer 1B will be disconnected for the period of repairs. Remove relay paddles, short out CT's and instrt isolation strips on test switches as shown on attachment 1. Impact on the other i protective functions was evaluated and found not to prevent unit operations.
Copies of the marked-up Control Wiring Diagrams, drawing 8770 B-327 Sheets 864 884. 885.878 and 899 (Attachment 1) reflect the tempcrary changes required. le
- muired changes are as follows:
a) Main Transformer 1B (GSU 1B) dedicated differential protection CIA and the fault pressure relay (EP) alarm shall be taken out of service, b) The current transformers on GSU IB shall be isolated. The relay settings for the string bus differential protection zone ~S1". and the differential protection zones Al & B1 settings will not be impacted by this change. In addition, since the Unit will be operating in this mode for a short
. time period, no relay setting changes are required for the following relays:
Out-of-step protection
- Generator leads protection
= Loss of field protection
JPN PSL SEES 96-068 REVISION 0 PAGE 9 0F 9
9.0 REFERENCES
- 1. Condition Report 96 2136
- 2. St. Lucie Unit 1 FSAR. Amendment 14 t
j 3. St. Lucie Unit 1 Technical Specifications, through Amendment 145.
- 4. St. Lucie Plant Drawing 8770-1199, Rev. 5
- 5. St. Lucie Plant Drawing 8770-1200. Rdv. 3 4
- 6. St. Lucie Plant Drawing 8770-1015. Rev. 8 l l
~
- 7. St. Lucie Plant Drawing 8770-B-327. Sheet 864. Rev.11
- 8. St. Lucie Plant Drawing 8770-B-327. Sheet 884.' Rev. 08
- 9. St. Lucie Plant Drawing 8770 B-327. Sheet 885. Rev. 22
- 10. St. Lucie Plant Drawing 8770-B-327. Sheet 878. Rev. 8
- 11. St. Lucie Plant Drawing 8770 B-327. Sheet 899. Rev.1
- 12. ANSI Standard C57.12.00-1987 IEEE Standard General Requirements for Liquid-Immersed Dis.tribution. Power and Regulating Transformers.
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1 TOLERANCE FOR ALL DIMENSIONS IS +11/2" U.N.O. s GASKET MATERLAI*
- 2. CARSON STEEL MEMBERS SHALL BE ASTMA38 .
M I % MIN) 3.-PLYWOOO SHALL BE COATED WITH FIRE RETARDANT COATING. ' l.. INNER AND OUTER SECTIONS OF PLUG SPALL BE SCREWED TOGETHER g ENCLOSURE PANEL USING A MINIMUM OF 4 SCREWS 1* OR 's.25
- LONG.
l.-GASRET SHALL SE TIGKn.Y FIT AG4<ST THE EDGE OF THE INNER & DUCT (TYP) SECTION OF THE PLUG AND Ga.uED TO THE SURFACE OF THE OUTER SFCTION CAULK SHALL BE PLACED AROUND 1NE EDGE OF THE INNER SECTION PRIOR TO INSTALLADON OF PLUG. SECT. A (AS SHOWN) 5.-ORILL 7 tie" OIA. HOLES ON THE ENCLOSURE PANELS. PLYWOOD & PLAfES FOR THE 318" DIA. SOLTS
- 7. 80LTS SHALL DE ASTM A307 ANDgEE READEDDETAILS ROOS SMALL FOR BELOCATOn.
ASTM A38. SECT. B (AS NOTED) 3#4*m4* s4* AS REOUIRED) WOODEN SLOCK. WITH A 7/16* DIA. HOLE IN TM SHALL BE PLACED SETWEEN THE EXTERIOR SURF ACE OF THE ENCLOSURE PANEL AND THE FLAT WASHER / NUT OF TNE BOLT.
- 8. 80LTS SHALL SE SNUG TIGHT 9..AFTER REMOVAL OF TEMPORARY PLUGS. HOLES DRILLED IN ENCLOSURE PAf#15 SHALL SE REPAIRED IN ACCORDANCE WITH DRWG. Paan 2 of thin attachment
- 10. ALL MATERIAL SHALL BE PROCURED PC 4 MINIMUM.
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! BO E R E' A R 2 5- A - i i L WA91-ER AbD 6A9KET TO COVER FXISTNG BOLT HdLC. l 2. SNU6 TIGHT BOLTS WITHOl>T CRUSHNG GASKET MATL. l 3. DOLT HEAD SHALL DE ON NSDE OF PLEbtM
- 4. ALL MATERIAL SHALL BE PC-4, OR DETTER.
i - 1 4
at 55 C/FOA et 65 C), double secondary winding, 240-6.9-4.16 kv. The 6.9 kv secondary is rated 12.6/16.8/21/23.5 MVA, OA/FA/F0A/ at 55 C/FOA at 65C; the 4.16 kv secondary is rated 8.4/11.2/14/15.7MVA, 0/./FA/F0A at 55 C/F0A at 65 C. The startup transformers are sized to accommodate the auxiliary loads of the - unit under any operating or accident condition. Each set of startup transformers (1A-2A,1B-2B) is provided with a manual switching arrangement which permits paralleling of 4.16 kv busses of one power train division (A or B) of Units 1 and 2 under administrative control. In the event one of the I four startup transf ormers has to be removed from service for repair, the 4.16 kv power to both Units 1 and 2 could be paralleled to facilitate continued operation of both units. A single startup transformer is adequately sized to accommodate the auxiliary loads of both units when aligned as described above provided operating procedures limit load sufficiently to prevent overloading the startup transformers or exceeding the short circuit ratings of the switchgear. If it should ever be necessary to align one startup transformer to supply 4.16 kv power to both units, ap'p ropriate operating procedures will be developed to assure that the startup transformer is not overloaded should an accident condition arise. 8.2.1.4 Main Generator The station main generator is a 1000 Hva Westinghouse generator which provides power to the offsite transmission network at various loads to a maximum of 850 MWe. The main generator data are given by Table 8.2-1. The main generator is direct connected' through a 22 kv, 28,000 ampere isolated phase bus to the main transf ormers, where it is stepped up to 240 kv and then tied to one bay of the outdooor switchyard. The main transformer bank consists of two (2), three-phase transformers, 475 Mya each, forced oil and air (FQA) cooled at 650C temperature rise, connected in parallel, with separate cooling equipment such that any one transformer can be uprated to 632 Hva at 650C rise if the other transformer is out of service and all the cooling equipment is applied to the remaining transf ormer. These transformers are provided with lightning arresters on the high voltage side. The generator isolated phase bus is forced air cooled and is rated f or both normal (two main transformers in service) and emergency operation (one main transformer out, the other uprated to 632 Mya) all at 650C rise. Two 100 percent capacity sets of cooling equipment are provided. 8.2.2 ANALYSIS In response to an NRC letter d'a ted 8/8/79 expressing a concern that the offsite power system (grid) and onsite electrical distribution system is of ouf ficient capacity and capability to automatically start and operate all required safety loads, voltage analyses were performed. See Reference 1. The results verified the adequacy of the design. The following reliability considerations satisfy the requirements of AEC GDC 17 and Safety Guide 32 for offsite power systems and minimize the probability of power failure due to faults in the network interconnections and the dsSociated switching. l 0154F/5 8.2-2 Am. 10-7 /91
4 7 FPL To: R. J. Acosta Date: Sept. 7,1996 From: R. G. Leckey Dept: JA-JB
Subject:
Nuclear Safety SPEAKOUT Action items Ref: (1) T. F. Plunkett Memo to NRC L-96-160, dated June 20,199S ' (2) NRC Inspection Report 96-05, dated May 31,1996 (3) Morgan, Lewis & Bokius LLP Assessment, dated May 31,1996 1 I A Self-Assessment of the actions taken by Nuclear Assurance to address commitments, recommendations, and comments, contained in the referenced documents has been completed. Attached is a copy of the Self-Assessment which indicates that allissues identified have been adequately addressed. l l l l This Self-Assessment also documents actions necessary to close-out JB AIT #'s 960304, { 960302, and 960301. Action item # 960303, due June 1,1997; was opened to track the latest date to complete the next Self-Assessment. . R. G. Leckey Supervisor SPEAKOUT RGUrgt Enclosure i l cc: M. S. Dryden, J. Luchka, J. Gallagher, G. Wiles, J. DeAngelis (/ I
.Y
- 1 SELF-ASSESSMENT OF ACTIONS TAKEN TO ADDRESS NUCLEAR SAFETY SPEAKOUT NRC INSPECTION AND INDEPENDENT ASSESSMENT ACTION ITEMS (Completed Sept. 6,1996)
ITEM DESCRIPTION (C= Commitment, R= Recommendation, REQUIRED DATE O= Observation) __ SOURM _ DATE ACTION TAKEN/ REQUIRED COMPLETE
- 1. Increase SPEAKOUT staffing (C). TFP L-96-160 Early Sept 96 (a) Appointed Supervisor responsible for SPEAKOUT at all (a) July 1,1996 I locations.
(b)Added one fun-time Investigator at PTN and PSL(Total of two (b) Sept. 3,1996 1 at each location). Investigations at JB will draw resources as [' needed. l
- 2. Improve feedback to concernees by providing TFP L-96-160 Early Sept. 96 (a)NSS-1 revised to provide additional guidance on content of Sept. 3, 1996 more detailed response letters (C). response letters (par. 5.9.2).
(b)NSS-1 revised to require new supervisor to review and approve au concem response letters prior to SRC review and transmittal (pars.5.9.1, 5.9.2). (c)NSS-1 revised to clarify SRC responsibility to review most response letters prior to transmittal (pars.3.4, 5.8.3). (d)NSS-1 revised to provide for a verbal debrief with the concemee in addition to the response letter when warranted (par.5.9.6).
- 3. Parform approx. annual Self-assessments of TFP L-96-160 Early Sept. 96 (a)An independent assessment of SPEAKOUT was performed by (a)May 31,1996 SPEAKOUT to determine program Morgan, Lewis, & Bockius LLP.
effectiveness (C). (b)This Self-assessment completed 9/6/96. (b) Sept. 6,1996 (c)The next Self-assessment of SPEAKOUT win be completed by (c)May 31,1997
, , May 31.1997.
(d)SPEAKOUT personnel attended a Self-Assessment Workshop (d)Aug. 21,1996 August 21,1996. (e)NSS-1 was revised to provide for periodic Self- (e) Sept. 3,1996 Assessment (par. 7.1) including the use of scheduled interviews I for the purpose of Self-Assessment (par. 5.3.2).
- 4. SPEAKOUT recommendations win be tracked TFP L-96-160 Early Sept. 96 (a)NSS-1 revised to require tracking of all SPEAKOUT Sept. 3,1996 through final disposition (C). recommendations to final disposition (pars. 3.2.10, 3.3.21, 5.10). '
(b)NSS-1 revised to provide for processing SPEAKOUT recommendations via Condition Reports (CRs) when confidentiality will not be compromised. (c)NSS-1 revised to provide management follow-up when recommendations late or not imolementedfoars.5.10.3. 5.10.41. i 1 l
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ITEM DESCRIPTION (C= Commitment, R= Recommendation, HEQUIRED O= Observation) SOURCE DATE DATE ACTION TAKEN/REOutRED COMPLETE
- 14. Administrative features and turnaround M L&B Assess. N/A (a)See items 1,6,7 above.
edversely impacted by reduced resourt'es(O). Sept. 3,1996
- 15. Instructions do not addres's actions by M,L&B Assess. N/A SPEAKOUT to ensure no retaliation against (a)See item 9 above. (a) Sept. 5.1996 cmployee after concem dispositioned(O). (b)Added reference to NRC Policy Statement (par. 2.1.10). (b) Sept. 3,1996 (c)lncluded in NP.800, Rev.4.
(c) Sept. 3,1996 (d)The SPEAKOUT orientation video has been updated by the (d) Complete President and emphasizes his policy of non-threatening behavior towards SPEAKOUT participants. (e)PSL AP 0010519, (pars.8.2.2,8.1.3}; PTN 0-ADM- (e) Complete 002(par.5.1.1,5.2.2); and IP.802 (pars.5.1.1,5.2.2) clearty establish and communicate the policy. (f)NSS-1 (pars. 5.2.1,5.4.2.3) provide for confidentiality so far as (I) Sept. 3.1996 practicable throughout the process.
- 16. Feedback to the concemee may not be M L&B Assess. N/A sufficient (O). (a)See item 2 above. Sept. 3,1996
- 17. NSS-1 does not address measures of M,L&B Assess. N/A (a)See item 3 above. Sept. 3,1996 eif rctiveness for SPEAKOUT(O).
(b)NSS-1 was revised to include performance indicators (par.7.1).
- 18. NSS-1 does not address the role of M L&B Assess. N/A prioritization in management of SPEAKOUT (a)The Supervisor is responsible for prioritizing concem Sept. 3.1996 workload (O).
investigations (pars. 3.3.3, 5.5)
- 19. SPEAKOUT addresses concems M,L&B Assess. N/A retrospectively rather than prospective!y. (a)This is not considered a direct SPEAKOUT accountability. The (a) Sept. 3.199 .
Instructions do not address training of necessary policies and practices are well documented in supervisors or managers with respect to SPEAKOUT procedures and management policy statements, as
'a referenced above(NP-800 TFP Video, TFP Memo, etc.). This is mInaging employee safety concems(O).
an item that will be reflected in Self-Assessment results. (b) Mat /Supv. Civil Conduct training covers this topic. (b) Ongoing
- 20. Handling of contractors is not specifically M.L&B Assess. N/A (a)NSS-1(par.1.0) and NP 800 have been revised to more (a) Sept. 3,1996 cddressed(O).
specifically include contractors in all aspects of the program. No distinction is made or intended relative to processing contractor concems vs employees. (b)The Video used to orient contractors, and for their exit (b) Ongoing interviews, makes it clear that contractors may express concems to FPL SPEAKOUT. Previous data indicates that contractors have been included and do participate.
- 21. NSS-1 does not address interaction, M,L&B Assess. N/A ov;rsight, or coordination of contractors (a)JB OA performs a planned review of major contractors DOL 6.'t. 3,1996 211 activities. .
ECP's(O). (b)The pertinent regulatory reqcirements are incorporated into all aDDiicable procurement documents. 4
.. 2 ITEM DESCRIPTION (C=Cammitment, R= Recommendation, $1EQUIRED O= Observation) SOURCE DATE DATE ACTION TAKEN/ REQUIRED COMPLETE
- 22. Procedural safeguard for maintaining M,L&B Assess. N/A confidentiality need reconciled with curtent (a)See items 1 and 7 above. Ongoing staffing' practices (O).
- 23. SPEAKOUT could investigate more concems M,L&B Assess. N/A (a)See item 1 above. Sept. 3,1996 in-house with additional resources (O). (b)Once the current backlog and aging time is reduced, consideration will be given to bringing more investigations in-house.
- 24. Management should review staffing at PTN M.L&B Assess. N/A (a)See item 1 above. Aug.1,1996 znd PSL(O).
- 25. No formal training provided to employees of M,L&B Assess, N/A (a) Training in selected topics was provided to all SPEAKOUT (a) Complete other departments investigating SPEAKOUT concems(O). investigators and some other individuals on July 25,26 and Aug.
21. (b)See' Item 13 above for additional discussion. (b) Sept. 3,1996 NOTE: Since it is not possible to predict the specific resource needs from other Depts. In advance, the above measures are considered more effective than mass training or other possible actions.
- 26. Training for new investigators should be M.L&B Assess. N/A (a) Training in selected topics was provided to att SPEAKOUT (a) Complete cor.sidered(O). Investigators on July 25,26 and Aug. 21.
(b)See item 13 above. (b) Sept. 3,1996 (c)NSS-1 includes adequate training guidance. (c) Sept. 3,1996
- 27. Management should reconcile expectations M.L&B Assess. N/A (a)See items 1,6 and 10 above.
with respect to quality! timeliness of Sept 3,1996 (b) Performance measures (par. 7.0) will be monitored to evafuate investigations with avaitable resources (O). ettectiveness.
- 28. NSS-1 does not address prioritization among M,L&B Assess. N/A (a)See item 18 above.
multiple Class 1 concems and dedication of Sept. 3,1996 (b)ltem 1 also will obviate this issue. NSS resources (O).
- 29. Some administrative portions of the program M.L&B Assess. N/A (a)See item 1,6,7,14.24, and 27 above.
are not being accomplished because of Sept. 3,1996 resource limitations (O).
- 30. The program appears understaffed to meet M.L&B Assess. N/A (a)See item 29 above. Sept 3,1996 all stated objectives (O).
31, NSS is not audited. Self-Assessments may M.L&B Assess. N/A NOTE: Due to the sensitivity of the SPEAKOUT Information. Ongoing be effective in identifying trends before weaknesses develop (O). audits would add a potential vulnerability to the confidentiality. (a) Performance indicators and Self-Assessment results will be monitored to determine the need for independent audits. 5
ITEM DEZCRIPTION , (C= Commitment, R= Recommendation, ilEOUIRED 0 DATE O= Observation) SOURCE DATE ACTION TAKEN/REOUIRED COMPLETE
- 32. The program may be less effective irt M,L&B Assess. N/A (ra)ltems 1.6,8,10,11.18,23,27,28,29,30,etc. above address this Sept. 3,1996 addressing non-safety issues in a timely issue.
manner (O).
- 33. Minimal feedback in response letter (O). M,L&B Assess. N/A (a)See item 2 above. Sept. 3, 1996
- 34. Completeness of documentation varies M.L&B Assess. N/A (a)See items 1,7,10,11,12 and 23 above. Sept 3,1996 between locations (O).
- 35. Cuality of Investigations not reviewed by SRC M.L&B Assess. N/A (a)NSS-1 revised to clarify SRC responsibilities (par. 3.4). Sept. 3,1996 is questionable (O). (b)AR investigation r0 ports will be reviewed and approved by the Supervisor (par. 3.2.14).
(c)See items 1,7,10,23,32 above.
- 36. Classification of concems at aillocations not M L&B Assess. N/A (a)The Supervisor, in addiHon to review by the Director, win review Sept. 3,1996 consistent (O).
and approve all classifications (pars.3.1.1, 3.2.5, 5.5). 37, Appreciation Centers unmanned while M,L&B Assess. N/A (a)See item 1 above. Sept. 3,1996 investigator performing other duties (O)._
- 38. Practice of providing concemee identity to M.L&B Assess. N/A (a)The identity will be revealed to the assigned Dept. only when it Sept. 3,1996 Security not consistent (O). Is necessary to conduct the investigation (pars.5.2.1.2,5.2.1.4, 5.6.2, and 5.7.1).
(b)See also items 5,22, and 23 above.
- 39. Dissemination of lessons learned, such as M,L&B Assess. N/A (a) Monthly reports, performance indicators and self-assessments Sept. 3,1996 trtnds or opportunities to improvo SPEAKOUT wiu address this issue (pers, 5.11, and 7.0),
performance, is informal (O). (b)See items 3.17, and 31 above.
- 40. Feedback not solicited from concernees(O). M,L&B Assess. N/A (a)Some self-assessments will be structured to include concernee Sept. 3,1996 feedback (par. 7.2), including Scheduled Interviews (par.5.3.2).
(b) Verbal debrief of concemees will provide real-time feedback (par. 5.9.6). 41 Emphasis on reducing backlog and M,L&B Assess. N/A (a)See items 1,6,10.14,23,32, etc., above. Sept. 3,1996 tumaround by SPEAKOUT may have lessened r* view of investigations by other Depts(O).
- 42. Periodic feedback to apprise concernee of M,L&B Assess. N/A (a) Concern aging will be tracked and feedback provided after 45 Sept. 3,1996 st:tus of investigations not consistently days (par. 5.9.5).
provided(O). (b)ltem 1, etc., will also address this issue. 6
ITEM DE!CRIPTION (C= Commitment, R= Recommendation, NEQUIRED DATE O= Observation) SOURCE DATE ACTION TAKEN/ REQUIRED COMPLETE
- 43. Concems are substantiated but changes are M.L&B Assess. N/A (a)lmprovements have been incorporated in NSS-1 to improve Sept. 3,1996 not rnade(O). SPEAKOUT's follow-up to recommendations. See item 4 above.
(b)Self-Assessments and/or Indicators will be used to moedtor the effectiveness of these revisions (par. 7.0).
- 44. Revise NSS-1 to reflect manpower resources M L&B Assess. N/A (a)See 7,24,27,29,30,32, etc., above. Sept. 3,1996 r nd current practice (R).
- 45. Evaluate the scope of conce:ns accepted to M L&B Assess. N/A (a)See 7,24,27,29,30,32, etc., above. Sept. 3,1996 ensure scope matches resources. Consider (b)ltems 23,25, and 32 also address this issue.
matrMog dedicated employees from other Dep.t Centralizat;on of some administrative P.S s r. ly be possible(R).
- 46. Provide more information to concernees on M L&B Assess. N/A (a)See items 2,10,16,33 abc ^ Sept. 3,1996 the results of the investigation and bas!s for conclusions (R).
- 47. Consider use of CR's for processing M L&B Assess. N/A (a)NSS-1 was revised to include the use of CR's for some Sept. 3,1996 recommendations and/or concerns recommendations (par. 5.10.2 and for some conditions identified cnonymously(R). by SPEAKOUT during an investigation (par. 5.1.1.1).
NOTE: It was considered and determined inappropriate to enter concems directly into the CR system for processing, since presumably the concemee would have done so had he felt that would adequately address the problem.
- 48. Consider augmenting SPEAKOUT staff with M.L&B Assess. N/A (a)The SPEAKOUT staff has been augmented with qualified, Sept. 3,1996 cmployees from !!ne organizations for a fixed experienced personnel (See item 1 above).
period of time (R). (b)ltems 13,23, and 25 alsoaddresss this issue.
- 49. Consider developing classification examples M L&B Assess. N/A (a) See item 36 above. Sept. 3,1996 from past practice as a guide (R).
- 50. Revise NSS-1 to specifically include M.L&B Assess. N/A (a)See item 20 above. Sept. 3,1996 contractors in the scope of the prograr.i(R).
- 51. Consider reviewing contractor ECP's and M,L&B Assess. N/A (a)See item 21 above. Ongoing handling of attegations(R).
- 52. Consider formalized training for any additions M L&B Assess. N/A (a)See item 26 above. Sept. 3,1996 to the iPEAKOUT staff (R).
- 53. Consider periodic assessments or audits of M L&B Assess. N/A (a)See item 31 above. Sept. 3,1996 the SPEAKOUT program (R).
7
4 o PTN SPEAKOUT H&I CONCERN
SUMMARY
(11/13/96) DESCRIPTION / YEAR 1992 1993 1994 1995 1996 TOTAL YTD (92-96) TOTAL NRC 14/6 14/12 7/7 9/3 11/9 ALLEGATIONS 55/37 (UNIT 3/ UNIT 4) NRC HEI 1/0 5/5 0/0 0/0 1/1 ALLEGATIONS 7/6 (UNIT 3/ UNIT 4) PTN CONCERNS 180 169 154 75 45 623 RECEIVED (TOTAL)
% SUBSTANTIATED 33 33 29 15 9 28 PTN HEI CONCERNS 1 5 9 9 6 30 RECEIVED
% SUBSTANTIATED 0 2 4 2 2 YO l
i NOTES: 1. NRC fiscal year is Oct. 1 - Sept. 30.
- 2. FPL is calendar year. ,
- 3. NRC data is through May 1996 (8 Mo.). {
- 4. FPL data is through Oct. 1996 (10 Mo.).
- 5. FPL substantiated H&I does not necessarily infer H&I ;
for engaging in protected activity. l I i I l i ptnaleg-Nov. 13, 1996
s s PSL SPEAKO'UT H&I CONCERN
SUMMARY
(11/13/96) DESCRIPTION / YEAR 1992 1993 1994 1995 1996 TOTAL YTD (92-96) TOTAL NRC 7/5 3/3 6/6 13/6 35/19 64/39 ALLEGATIONS (UNIT 1/ UNIT 2) l NRC HEI 1/0 0/0 1/1 1/1 4/2 7/4 ALLEGATIONS 1 (UNIT 1/ UNIT 2) l 1 PSL CONCERNS 144 120 132 70 83 549 l RECEIVED (TOTAL)
% SUBSTANTIATED 37 30 34 44 37 36 PSL HEI CONCERNS O 1 3 4 9 17 RECEIVED
% SUBSTANTIATED 0 0 33 25 33 29 NOTES: 1. NRC fiscal year is Oct. 1 - Sept. 30.
- 2. FPL is calendar year. '
- 3. NRC data is through May 1996 (8 Mo.).
- 4. FPL data is through Oct. 1996 (10 Mo.).
- 5. FPL substantiated H&I does not necessarily infer H&I J for engaging in protected activity. ;
)
I i pslaleg-Nov. 13, 1996 l
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_. __._ _ _ . _ . . _ . _ _ _ _ . . _ . ~.__ _~ __ _ _ _ _ _. _ _ _ _ _ .__. _ TABLE OF CONTENTS r rene SECTION I VICE PRESIDENT - ST. LUCIE PLANT ORG ANIZATION ' Vice President Organization I Business Systems Department - loca 9166 2 Contracts - Loca 9167 3 , Corrective Action -Ieca 9168 4 : Management Information Systems - Loca 9048 5 6 Resource Control- Locn 9123 Licensing Department- Locn 9041 7 Materials Management Departm-nt - Locn 9046 , 8 9 Iluman Resources - Loca 9122 10 ; Site Engineering Department - Locn 9256 II l Quality Assurance- Loca 6270 ' SECTION II PLANT GENERAL M AN AGER - ST. LUCIE PLANT ORGANIZATION Plant General Manager Organization 12 ; 13 Maintenance Group Electrical Maintenance Department - Loca 9103 14 ; instrument & Control Maintenance Department - Loca 9102 15 16
- Maintenance Services - Loca 9162 17 ,
Rotating Equipment Department (Pumps, Motors & Fans) Department - leen 9163 Valves and Welding Maintenance Department - Loca 9165 18 . 19 Operations Group 20 Chemistry Department - Locn 9106 21 IIcalth Physics Department - Locn 9104 22 Operations Department - 9107 t 23 Operations Support Department - Loca 9152 ' Work Control Department - Locn 9115 24 SECTION III SITE SERVICES MANAGER - ST. LUCIE PLANT ORG ANIZATION 25 Services Manager Organization Information Services Department - Locn 9109 26 ; Land Utilization Department - Locn,9257 27 Protection Services Department - Locn 9129 28 29 Security Department -Imen 9020 i 30 Training Department - Locn 9127 e -
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St. Lucie NucIsar PI nt Vice President's Organization VICE PRESIDENT IT tIICIP Pl ANT 5 A STAI L
~
V P. SFCRET AItY K HTST i , , , , , ,_______________, PROCESS STEAMGEN RFPLA(Y ffUMAN RESOURm l t lCENSINO MANACER M ATERIALS MANAGER PLANT OFNFRAI MANAGFR MANAOPR l SFRVICES MANAGFR SPECIAttST PROF MANAGER AMA R g E WFINK AM G f 90t$$Y ISCAROtA R StPOS I C MORGAN
. Dl.FADOPN I VOORIFPS R E DAWSON
- I l
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$UPER VISOR MAINTENANCE MAINTENANCE OPERATIONS 3 K llORE A SPPGAIJST MANAOPR CONTROE. M A'4 ACPR T G RREINBFRG ,,
MANAOFR I C GALLAOltFR l
)W ttOt.T pg pg lotINSON O h WOOD l 9 MARCItESE T A DtLLARD StTE ENGINPERINO I N.FritW ACTION 8 ANDUTR REATION El ECTRICAL ogEMISTR Y MANAOPR j stesRVisOR stnRvison suPFRvisOr D 8 81FNVFR
"" G l. BOtl5R A I W KORTE o pt FAtq RN R I
$1TF QUAT ITY PRO 1FCTION SFRVICFS " A MANAGMENT INF Sq gpRyy50R N ALIII NYIU ACTINGl a C $tlPERVISOR ggrypRyggog SYSTPMt StIPFRVisOR ggg ' I !
JfM A PAWLEY IlFBtOIANAN g D M CAI ABRFSE VI5ff0R3 0ENTFR ! e SFCtqttTY OPFRATIONS StfPFRVtSOlt MAINTFNANCE ga gyogop4 RE50tCACE CONTROL PROCFDURES StgPRVisOR StMRVism styFRVisOR OPEN C D MARPtr e iaFROUx T R AINING MANAGFR MAINTFNANCE SilPPRVISOR SFRVKT5 SUPFRVISOR R O FNFINGlR R FPFOETTE PRPDtCTIVE MAINT StlPFRVISOR R R SETILTtlORPE ROTATINO PQtRPMFNT StIPFRVISOR D G PNORIS19 , i vAs.vEs a WFLINNG suPPRvisOR I. N MOTLEY g, y SEPTEMilER 10,1996 REV O
St. Lucie Nuclear Plant. Business Systems Group VICE PRESIDENT
- ST .1.tlCIE Pl. ANT J A. STAl.l.
F I.oc.9166 BUSINESS SYSTEMS MANAGER R. E. DAWSON loc.9167 Ioc.9168 Im 9MR loc.9123 ge 91% CORRECTIVE ACTION MANAGMENT INH)RMAIf0N RESOURCE CONTROL SYSTEMS SUPERVISOR I AN O W1RACTS SUPERVISOR SilPERVISOR ! T.O KRI:lNBERG D. M, CALABRESE R.W.IIEROIIX
- I" " 'I '
OPEN i i l i t Page 2 SEPII.MDER 10,1996 REV O i
St. Lucie NucI: r PI:nt Business Systems Department Contracts Section I,ocn 9167 IlliSINESS MANAGER R. E. DAWSON (UNTRACTS SilPliRVISOR T. G. KREINBERG CONTRACTS AGENT OPEN PIANT TECIINICIAN L N. GRAYBilSil SliPil-Mill R 10,1996 REV 0 p g, y
.(
St. Lucie Nuclear Plant Business Systems Department Management Information Systems Section , LOcn 9048 I i DUSINESS MANAGl:R j R. E DAWSON ! i MANAGMENT INFORMATION SYSTEMS SUPERVISOR D M CAI.ADRESE I.AN ADMINSTRATION API't.lCAI!ON IMIVEl.OPMENT ANAL.YSTS ' R. K. ANDERSON D. I DOTSON D DPOWN - J C. Gl. ASS M DIXON M l IlORTMAN OPEN J P.MCGl.ENN OPEN I
+
SEPIEMilER 10,1996 REV O Page 5
i t St. Lucie Nuclear Plant i Resource Control Department ( Locn 9123 I BUSINESS SERVICliS MANAGER 1 R. II. DAWSON t [ [ RESOURCE CONTROf. SUPERVISOR R. W. IIEROUX ! 1 ACCOUNTS PAYABLE BUDGET TECIINICIAN COST ANAI.YSTS SUPERVISOR. J. A. I.AllERA P.W.KFNNEDY ; l..LEN E. MESIJN i C. PITI' MAN J. S SlJMM t I i I h t SEPTEMBER 10,1996 REV 0
%6 i t
St. Lucie Nuclear Plant Licensing Department
~
Location 9041 VICE PRESilENT ST.1.tK1E Pl. ANT 1 A.STAl.I. l.ICENSING MANAGER E. L WEINKAM l.lCENSING ENGINEER I.fCENSING I.fCENSING ENGINEER OPERATIONS EXP NRR ANAI.YSTS TECIINICAI, SilPPORT COMPI IANCE EN(IINEf'R R. L DIETZ S P. TREPANIER E. I fil:NKIN C. F. ITRRIDAY G R. MADDEN OPIN R. NORI.E P. T. Qtlit.l .IN e-SI Pil'.Mlli R 10,1996 RI:.V 0
e St. Lucie Nuclear Plant Materials Management Department LOcn 9046 SITE VICE PRESIDENT J. A. stall MATERIALS MANAGER G. J. BOISSY I ; CliNIRAI. RECI lVING DEDICATION ANAI.YST INVENTORY CONTROL ISSIfliS SUPI'RVISOR PROCllREMENT Stirl{RVISOR SilPERVISOR SilPERVISOft D. K. QUll.TY A R NFIIRFRGI'R M.G UI.I. MAN L A.R(XiERS W. A.1.YNCII TECIINICIANS PROCitRI: MEN I' TECllNICIANS ANALYSTS AGENTS W. C. ARMES S. D. BARRY d. R O ENS J D. CllESSER T. E. EVANS J. C. EDGAR R. J. C1101 EWINSKI S. B. PINKSTON D A.KORNSTADT C. J. IIARRIS E. G. PRICF G RICIIARDS C, D. SUMMERS T.M SilFil. W. D. WillTE TECllNICIANS TECIINICIAN D. A. BIRNBAUM J. D. CllAUVIN R. J. CONKI IN T. L CIIVII.A D.M.GItIBKA D. K. COX P. S. POUI.OS N. A.QUF.SADA
. W. M. QUlGI.EY SEPTEMBFR 10.1996 REVO Page 8
St. Lucie Nuclear Plant . Site Iluman Resources Department Location 9122 , III! MAN RESOURCl3 ; MANAGER I. C. MORGAN i i EMPI.OYMENT IADOR REI ATM)NS , ADMINISTRA1DR ADMINISTRATOR TEO M M A. A.UEllPING C. D. SCOIT K. M NEI. SON t b I r l I SI:PTI:MllI?R 10,1996 RiiV 0 I
St. Lucia NucI cr Plant Site Engineering Department Location 9256 psi.RNomP Rmo MANAGER D 1 DENVER AID 01NISIRAllVE Pt ANT PNGINFER OPS St# PORT PRoyCy PROJECT ENOR SYS ENOR EFPR VISUR MANAGFR ENOR SUPPRVIMMt FNGR FSAR h84tMT RtAg ht4NAGPR R L CtRECH R D Gtt # P FIN FORD K MulttNDROO M SNYDFR f WFST RE ACTOR ENGR DRAWING'JPDATE l l l l tgAD FSAR Sys l l gyAD C3VIL Efq;R 8434GN B A$ts , PRottNtPMEN T P Sernes cohyONENT PRIMAR Y SUPPR VISOR StFERVISOR ENOR SUPV C.G OTARRM1 R Cseeis styy g gy DE GATES g pytyppg *EN A 7 AT A R WiNNARD 8 IIOGE , y M Mosheven g pan gyngygg R ht Kleen E E Civu Fagenerers DR Enges lac Eag e p
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St. Lucis Nucienr PI:nt Site Quality Assurance Department Location 6270 t i SITE QtlAllTY MANAGER 1 1.W.DIAIX)W QtlAl IlY silPFRVISOR QtiAI.lTY SilPERVISOR QtlAl.lTY StJPERVISOR AtJDilS/ PERI ~ORMANCli INDEPENDENT TECitNICAI. Q41Al.ITY CONTROL. MONITORING REVIEW G A. SCllNEDII j D I.OWENS R. IMi I A ESPRIEI.l.A ! I l HEARROR K HtITI.ER ^ D 1811EY D P.KOENNICKE I RISS JIOWERY C. NORRIS T. DWYER I.MCNEY D PARKS B FEINBERG S. RlilA OPFN D. GINGRAS R WAl ClltiSKI OPEN R. IIAWIJiY I *^IIS W.IIAYS R. WEIS A.IfoSIE G. INGRAM M Melt.EY D. MEI.ODY R. Mll l.f?R R. MOSS ! I PANESSA R. SPARKS E R. STORMS A. IIREVITTI OPfW f St Pil MDl_R 10,1996 Rl!V O Page ll
i SECTION II t PLANT GENERAL MANAGER ST. LUCIE PLANT ORGANIZATION
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St. Lucis NucI2cr Plant Maintenance Group ' t Pl. ANT GENERAL. MAN AGICR J. SCAROI.A I MAINENANCE MANAGER , J. MARCIIESE , l
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.i I ELI!C1RICAl. ACTING I A C MAINTENANCli MAINTENANCli ROTATING EQUIP val.VES & WEIJMNO SUPFRVISOR SUPERVISOR PROCEDifRES SUPV SERVICES SifrV. SilPERVISOR StfPFRVISOR 6
W. KORTE A PAWEEY , OPEN R. FRECllETTE D.G ENGIISil 1. N. Moll.EY i I ' I A C PROC PREIMCTIVE MAINT ROTATING til.EC ICAL MECil N PROC WRITER WRITER WRITER A DELGADO H. R. SCUI.TIK)RPli SilPERVISORS II. DisilOP R. TOSCANO I W. NEEl.Y" l R. C. OI. SON PM SPECIAl.lSTS J.'G. BRADY
^ '
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i SEPIEMilER 10,1996 REV O Page11 i
St. Lucie Nuclear Plant Electrical Maintenance Department Locn 9103 MAINTENANG MANAGER L MARCIIESE EI.FCTRICAl. SUPERVISOR W. KOR111 A/C, IlOP, COMMON El ECTRICAI. StJPPORT El.ECTRICAI. UNIT I PRODUCTION iINIT 2 PRODUC1 ION SilPERVISOR ANALYST MAINT1?NANCI! SilPIIRVISOR SUPERVISOR SilPPORT R. l_ llOSKINS D. GILDERT R.1'NSI.EY
. II. GRINI7R A TRINGALI $1'Pil: Mill:R 10,1996 RIiv 0 Page 14
St. Lucie Nuclear Plant Instrument & Control Department Locn 9102 MAINTENANCE MAN 4(WR 86 i ACT9NU $N57RUMPMT A CONTROL mvesop A PAW 12Y
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St. Lucie Nuclear Plant , Maintenance Services 1.ocn 9I62 l i MAINIENAN(Ti i MANAGFR J. MARCllESh ; L I ! i MAINTENANCE SERVK13
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6 St. Lucie Nuclear Plant i Rotating Equipment (Pumps, Motors, and Fans) Locn 9163 i i f i i MAINTENANCE i MANAGER J. M ARClfESE } i ROTATING l' QUIP. j SUPERVISOR 6 D.G ENGl.lS11 i I
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CRANE SUPPORT TECII PRODUCTION SUPPORT f R. O. STOI .I. J . W. Mll. TON R. A. DFCKER ! l t t
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St. Lucie Nuclear Plant Chemistry Department Location 9106 ,
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PIANI GENERAI. MAN AGER JSCAROI.A , 5 OPI'. RATIONS MANAGFR 11.11 JOIINSON CIIEMISTRY SUPfiRVISOR D.11. FAUI.KNER I NVIRONMENTAI. PRIMARY SUPV PilRCIIASING/ DATA RADIOL OGICAI. SECONDARY WTP/ STP POI.ISIIER StiPERVISOR DATA MANAGEMENT MANAGMENT Erri UFRI'S SUPV SUPliRVISOR SilPERVISOR A. P. IlUTI.ER I. II. BURGIESS S. IlliOMSTRUP R. E. COX J. SEAGER D. A. IIARIE i P SENK)R IAB TECllNICIANS , E.R.00 STER D M. MAJEWSKI D. J. EISERT E. II. MEYER I J. R. GEORGE S. F. PEDDICORH W. M. IIUFFOR V. S SCIIWi!RI-~R G J. KINGSI.EY M. L SERRil~lO I M I.EBl.ANC W.li VOIJ. MAR ROTATED AMONGST SUPI RVisORS 51 PII: Mill.R 10,1996 REV 0 m._____.. _ _ __________ _________mm__ _. _ _ _ _ _ - - _ _ - . --------.+----e -e.~ - - - - - - r t-- -- - - - - _ - - - - _ _ _m - __ _ im-- _
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- SUPERVISOR I R.O.[Nf1NGER I
t ANALYSTS SRO DEVEI.OPMENT 11? CLINICIANS ' f R. F. CZACllOR R litKillES B. E. CAMPI,IN j M Gil.MORE K. KORT11 R I DAll.EY ' M KOGEl.SC11ATZ W. I. PARKS J VAI. DES l J. S. NAPIER G SMITil S M. Wilill:llEAD j S E. PATTERSON C SWIATI K R.M.PENNENGA C. WARD : M. D. POTTORIT t 4 SliPIEMllER 10.1996 REV 0 page 3 i ___ _ - _ _ _ - _ _ _ ___ - _ __ _ __ ____-.__- - ____ _ _.____ _ _ - _ __- - _ . .__._______2
St. Lucis NucI::cr Plant Work Control Department Location 9115 ,
. PLANT GENER A1.
MANAGER JSCAROI.A 1 ACTING WORK CONIROI. MANAGI'R [ C D WOOD I i 1 I I IMPL EMENTATION PI ANNIN(# PARTS DAII.Y SCilEI) Pl.ANNING SifrERVISOR SYSTEM SUPERVISOR SilPERVISOR StfPERVISOR gggg,y33 j J li ilAllGI:R A W. MARVIN A G MENOCAl. p g,, ggggggp OPS ROTA~llON-2 YRS I I I I I OPS MAINT SCilEDtJLING SCDI Dill.ING ANAL.YST I &C /El.EC PLANNING MECll Pl.ANNING PARTS PLANNING SPECI Al. PROJECTS COORDINA10R AtlAl.YST StfPERVISOR St!PERVISOR StfrERVISOR A PWO CI.OSEOllT R J. MAISANO SifPl:RVISOR
- j. S. IIONALDI R.11 MAYllEW P. J. SARNO R I. DAVIS P. N. CONNOI .I.Y A DI:ROY ROT A s fNut3f ATIONAR Y OUI AGE S(11EDUllNG MrANAtYST Pt.ANNPR'~ B W 9tASOME ipogNgrtAN3 P2 IMINICIANS
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Page 2 4 SI'P Tl Mill R 10.1996 RI:V O
I l l 1 SECTION III i SITE SERVICES MANAGER ST. LUCIE PLANT ORGANIZATION
'St. Lucie Nuclear Plant Services Group i
t t i
.1 SERVICES MANAGER i
D.( FADDEN ; [ [ i t INI'ORMA110N SERVICES l 1AND tlTILIZATION PROTECTION SERVICl3 SEClIRITY SilPl?RVISOR TRAINING MANAGER i SI)PI RVISOR StIPliRVISOR StIPERVISOR W. G. WlIITE M AI.I.liN i G.l BOUSKA OPEN l J. W. IlOI.T ! [ r E t i 1 t i I i-8 L i i i I Page 25 ; SEPIFMill R 10,1996 RIiv 0 i _ . _ _ _ _ __:.___.______ _ _ _ _ . . _ . _ _ _ _ . . _ _ . _ . .__m . _ . _ . ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____________.._________________.________1. ___m____ . _ .
c . St. Lucie Nucinar Plant ' Information Services Department l.0cn 9109 i f INiORMATION SERVICI:S SECTION SUPERVISOR J.Ilot.T ; i I I I l CONI NitlRATION AUDMNVISilALS PROO'DtIRES S11PFRVISOR NUCl. EAR REO)RDS/ i MGMI SUPERVISOR DOC.CONTRDL ; M. S. STOCKl:R S A VAI. DES SUPERVISOR 6 D. A. [1ROWN T. V. OSWAI.D SIiIIGR APIIICS , CONilGilRAllON ANALYSTS NUCI EAR RI CORDS MANAGEMENT TECllNICIANS I_ M IX)NGIIIA P A IIASil.E C. P VANDERSCllOT I 3 H^lIIIY J A. CIMINO J.G MANN T_ M MAITI.AND K.1 MANNIN(i M D Wil.l.IFORD PROCI:DifRES N. J. WEST WORDPROCESSING/1 R(i " TECIINICIANS t
^ IXX11MliNT CONIROI i II (. IIARANOWSKY WGNOWS M P DIMARCO 11 S Gil.MOUR D E NH !
J. l DUTCll!'R l C.Il GlilSON l PR(MT:DURI S PRODifCllON K l_ IIAl.VFRNON ; li:CIINICI ANS P.G llAMil. TON i M I l.ANI! I
. L. R. DAVIS V. L. McDANil 1.
K. A. W(K)D T. I TAYI.OR OPIN i SEPTl Mill R 80,1996 REV 0 Page 26
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c . . i St. Lucie Nuclear Plant Land Utilization Department Locn 9257 t i 1 1 Sisit sirr r. i ANu UTIIJZATM)N G l~ DOUSKA L
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.St. Lucie Nuclear Plant Protection Services Department Locn 9129 rRofECTION SFRVKYS SureRytsOR OPEN FtpF PROTECTION FMPR ENCY PREPARFM5% IIAZARDOUS MATERIAI $
MEDICAL /$AFETY FNVIRONMFNi CE24Pt. LANCE A I SUPPR M G1PERVISOR st ypRyg3OR $UPfaYlSOR Q A MrDANIFl. 1 MO9FR 8 M TOSSIN N 18 wtMTINO 9, o wiefwets. FME PROTFCIION ANAL.Y$f W H SANDFL fine P901FCTION ANAt YST R SPtWE SI'P11.MilFR 10,1996 RiiV O Page 28
St. Lucie Nuclear Plant Security Department
- I.ocn 9020 SE(11RITY stersvison w o winte TRAINING 3Ff11RfiY OPPRAT3ONS FITNE13 FOR DtlTY SPECIALIST ACff$$ (UNTROL (1)nRDINATOR SUPE 9 VISOR SPFCIAt IST R W CZARNFrat S P PLANTZ A R 011MMINGS I It At i FN SINFT SPFO At.tSTS R T SITNFR R L 905 KEY R F 00RST I A TA11EY l' age 29 SI Pil: Mill:R 10,19% RIN O m.____. _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____ _ __ . . _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _
_ _ __ . . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _________________________.__m
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b. C Operations Department Chronological Log Unit 1 SHIFT NUMBER: 871 NUMBER: 871 NUC POWER: 100 DATE: 9/18S6 DELTA T POWER: 100 SHIFT: PEAK MWE: 880 BOARD RCO: GASSER CEA GROUP 2: 7 DESK RCO: SWAN POSITION: 136 NWE: KLAUCK T AVG: 574 ANPS: SMITH BORON: NPS: 77[ HONEYSETT Xe WORTH. -2416 MODE: 1 CALCULATED SD MARGIN: >3600 l MAJOR MILESTONES OR ACTIVITIES TO BE PERFORMED DURING THE SHIFT: . MAINTAIN 100% STEADY STATE OPERATION AND PERFORM FIRE SYSTEM PERIODIC TRAIN B. l TIME LOG ENTRIES i I 15:00 ASSUMED SHIFT AFTER BOARD WALKDOWN AND TURNOVER ! i 15.05 l&C CHANGED THE PAPER ON THE CONTAINMENT PIG. IT HAD RUN OUT. CONTAINMENT PIG IS 1 OPERATING NORMAL, EXITED OFF NORMAL PROCEDURE. b 15:12 RECEIVED ANNUNCIATORS FOR FIRE PP START AND TLO RESERVOIR DELUGE, DISPATCHED ANPO, NPO, AND NWE. CALLED FIRE PROTECTION. 15:17 NWE REPORTS DELUGE OPERATING ON TLO RESERVOIR DELUGE, NO FIRE OR OTHER ABNORMAL CONDITIONS OBSERVED. INSTUCTED NWE TO ISOLATE DELUGE. 15:19 ANPO HAS SECURED THE FIRE PPS AND RESTORED TO AUTO. 15:20 BOB MC DANIEL IS INVESTIGATING THE DELUGE PROBLEM 15:30 RECEIVED ANNUNCIATOR E-11 CIRC WTR PP 181 BRG TEMP HIGH, DISPATCHED ANPO. 15:40 ANPO REPORTS 1B1 CWP OIL LEVELS AND LUBE WTR NORMAL TEMPERATURE INSTRUMENT TIS-21,22-1B1 IS READING 184 5 TO 186. THE OTHER CWPS ARE READING 173,177, AND 180. NOTIFIED RMM AND WILL MONITOR. 15 45 CONTAINMENT AIRLOCK SEAL LEAKAGE TEST HAS BEEN COMPLETED, SAT. 16 15 RECEIVED ANNUN. K 35, CEA DRIVE MG SET 18 LOCAL ALARM. D!SPATCHED NWE AND SNPO. 16:20 NWE REPORTS HI FLYWHEEL VIBRATION ALARM ON 1B MG SET, ALARM RESET, VIBRATION SEEMS THE SAME AS 1 A MG SET AND AMPERAGE IS MATCHED WE WILL MONITOR THIS MACHINE. 1C:57 START 1B HPSI PP TO FILL 1 A1,181 AND 182 SITS 17:06 SJAE RAD MONITOR OOS WHILE OBTAINING DATA 17:36 STOPPED 1B HPSI PP 16.3$ LATE ENTRY, THE STA HAS MADE A COURTESY CALL TO THE NRC, INFORMING THEM OF A MANATEE IN THE INTAKE. 17.09 LATE ENTRY. SJAE RAD MONITOR BIS AIR IN LEAKAGE IS 3 4 SCFM 18-Sep-96 1 \
/ /
Y
iO W M Operations Department Chronological Log Unit 1 SHIFT NUMBER: 871 18:20 'A' CHANNEL ESFAS FOR CIS IS OOS FOR AREA RADIATION MONITORING SYSTEM PERIODIC TEST 18.40 'A' CHANNEL ESFAS BIS 18:41 'C' CHANNEL ESFAS FOR CIS IS DOS FOR AREA RADIATION MONITORING SYSTEM PERIODIC TEST 19 01 'C' CHANNEL ESFAS BIS 19 02 'B' CHANNEL ESFAS FOR CIS IS OOS FOR AREA RADIATION MONITORING SYSTEM PERIODIC TEST
.) 19:20 'B' CHANNEL ESFAS BIS 19:21 'D' CHANNEL ESFAS FOR CIS IS OOS FOR AREA RADIATION MONITORING SYSTEM PERIODIC TEST 19 40 'D' CHANNEL ESFAS BIS 19.45 WHILE RESTORING INSTRUMENTATION FROM AREA RADIATION MONITORING SYSTEM PERIODIC TEST, FOUND THE ATI FAULT LIGHT WOULD NOT RESET. APPEARS TO BE A 'B' MSIS BISTABLE PROBLEM. (ATI FAULT WAS CLEAR AT START OF TEST) CALLED RMM AND 1&C.
19:50 DATA SHEET 1 AND APPENDIX B HAVE BEEN COMPLETED SAT FOR THE SIT FILLS. 20.30 l&C DETERMINED A S/G PRESSURE INSTRUMENT FAILURE ON 'B' S/G,'D' CHANNEL MSIS HAS CAUSED THE ATI FAULT. 20.45 DECLARED 'B' SG MSIS FOR CHANNEL *D' ESFAS OOS AT 1945. WENT TO BYPASS ON ESFAS 'D' . CHANNEL'B' MSIS, BYPASS ON 'D' RPS TM/LP AND LO S/G PRESSURE AND BYPASS ON 'D' AFAS 1
- AND 2 21:30 'B' S/G PRESS ON 'D' CHANNEL ESFAS HAS GONE INTO TRIP CONDITION. SIGMA FOR 'B' SG PRESSURE IS FAILED HIGH.
21:30 START FILLING PRIMARY WATER TANK LEVEL IS 13 6' 20 00 LATE ENTRY, START FIRE SYSTEM PERIODIC l 21:00 LATE ENTRY, COMPLETED FIRE SYSTEM PERIODIC SAT. 22:15 SECURED PRIMARY WATER TANK FILL, LEVEL IS 16 4'. I 22.43 HVA 3B BIS, BHR SURVEILLANCE RUN SAT. 22.45 ANNUN. 2-5,1D SAS/ SUPS TROUBLE, HAS COME IN 6 TIMES THIS SHIFT. 22 55 NO FURTHER ENTRIES THIS SHIFT
) TIME REVIEWER'S COMMENTS 15 49 Rewswed log, JP Honeysett 21 52 Renewed log. JP Honeysett j 6
k 18-Sep-96 2 i l l l
l l l
, Operations Department Chronological Log Unit 1 SHIFT NUMBER: 872 l
NUMBER: 872 NUC POWER: 100 1 DATE: 9/19/96 DELTA T POWER: 100 SHIFT: MID MWE: 880 a BOARD RCO: MCKENZIE CEA GROUP #: 7 DESK RCO: SANDERS POSITION: 136 NWE: CASIAS T AVG: 574 ANPS: BROWN BORON: 995 NPS: SANDY Xe WORTH: -2423 l MODE: 1 CALCULATED SD MARGIN: 33600 l 2 MAJOR MILESTONES OR ACTIVITIES TO BE PERFORMED DURING THE SHIFT: MAINTAIN 100% POWER 4 TIME LOG ENTRIES i 23.00 ASSUMED THE SHIFT, COMPLETED BOARD WALKDOWN. 01:12 DEC' ARED SJAE RAD MONITOR OOS FOR IN LEAKAGE CHECK, 4
) 01:14 DECLARED SJAE RAD MON 1 TOR BIS.
05:00 T. NEWHOUSE HAS REVIEWED THE APPLICABLE DOCUMENTATION ASSOCIATED WITH THE MD CHANNEL ESFAS CABINET. HE BELIEVES THE PROBLEM TO BE IN AN ISOLATION MODULE, SINCE NO MODULES ARE AVAILABLE HE WILL HAVE TO ATTEMPT TO REPAIR THE OLD ONE. HE WILL BEGIN WORK ON DAYSHIFT TODAY. d 05 05 DECLARED FR47-1 A OOS FOR l&C CALIBRATION. I 06:30 FR47-1 A WILL NOT CALIBRATE AT THIS TIME. l&C TO CONTINUE WORKING ON THIS RECORDER ON
- FRIDAY MlDS.
3 1 06:45 NO FURTHER ENTRIES THIS SHIFT. 1 TIME REVIEWER *S COMMENTS , 05:25 Reviewed log. J Sancfy, NPS
\
05:46 Reviewed log. H. Johnson 06:18 Reviewed Log PB Isaacs E 19-Sep.96 f y
1 J Operations Department Chronological Log Unit 1
. SHIFT NUMBER: 873 NUMBER: 873 NUC POWER: 100 DATE: 9/19/96 DELTA T POWER: 100 SklFT: DAY MWE: 880 BOARD RCO: ABERNETHY CEA GROUP #: 7 DESK RCO: SANDERS /BOYLES POSITION: 136 NWE: TAYLOR T AVG: 574 1 ANPS: SCALES BORON: 995 NPS: ISAACS Xe WORTH: -2423 MODE: 1 CALCULATED SD MARGIN: 33600 MAJOR MILESTONES OR ACTNITIES TO BE PERFORMED DURING THE SHIF1:
MAINTAIN 100% POWER TIME LOG ENTRIES 07.00 ASSUMED THE SHIFT. COMPLETED BOARD WALKDOWN. 07:05 DISCOVERED THAT ESFAS 'D' CHANNEL *A' S/G PRESSURE WAS BYPASSED NOT'B' CHANNEL AS PREVIOUSLY LOGGED. 07:08 RESTORED ESFAS 'D' CHANNEL'A' S/G PRESSURE. BYPASSED *B' S/G PRESSURE. NOTIFIED NPS, STA, NRC, OPS SUPV, OPS MANAGER AND PLANT MANAGER. 07:15 RECEIVED DDPS ALARM ON INCORE DETECTOR F-19 (STRING 42 LEVEL 1). NOTIFIED WALT MEAD OF RX ENGINEERING. 07 30 WALT MEAD INVESTIGATING ALARM ON INCORE DETECTOR F-19, 08 00 DECLARED SJAE RAD MONITOR OOS FOR IN LEAKAGE CHECK 08 04 DECLARED SJAE RAD MONITOR BIS. 08 25 ANPS CONDUCTED TAILBOARD ON l&C TROUBLESHOOTING 'D' CHANNEL ESFAS. 08:30 I&C STARTED TROUBLESHOOTING 'D' CHANNEL ESFAS, 08 40 l&C REPORTS THAT THE BISTABLE AND BLOCK MODULE FOR 'B' S/G PRESSURE WOULD NOT ACTUATE AS REQUIRED. INVESTIGATING CAUSE AT THIS TIME. 08.50 l&C REPORTS THAT CAUSE OF THE *D' CHANNEL ESFAS 'B' S/G PRESSURE BISTABLE AND BLOCK MODULE FAILURE WAS DUE TO A FAILED POWER SUPPLY. 09 50 DECLARED FUEL HANDLING BLDG VENT RAD MONITOR OOS FOR l&C FU.NCTIONAL. 09.55 COMPLETED BOARDWALK DOWNS AND REVElWED PAPER WORK BOYLES HAS RELIEVED SANDERS AS THE DESK RCO. 10.55 CORRECTION TO PREVIOUS 0955 LOG ENTRY. TIME SHOULD READ 1055 BOYLES RELIEVED
' SANDERS.
11.55 l&C HAS COMPLETED THE CHANNEL CHECK OF RSC-26-4, SPENT FUEL HANDLING BLDG. VENT RAD MONITOR. CHANNEL CHECK SAT. MONITOR BACK IN SERVICE. 13 25 SOURCE CHECK BE!NG PERFORMED ON FUEL HDLG BLDG VENT RAD MON 19-Sep96 1
y Operations Department Chronological Log Unit 1 SHIFT NUMBER: 873 13.30 SOURCE CHK OF FHB VENT MON COMPLETED SAT. 14.00 REACTOR ENGINEERING ENTERING NEW INCORE SETPOINTS BECAUSE THEY WERE DUE TO BE PUT IN AND IN RESPONSE TO DET F-19 ALARM 14 30 DDPS COMPUTER HAS SWAPPED TO THE BACK-UP COMP-2. NOTIFIED i&C PERSONNEL AND REQUESTED THEM TO INVESTIGATE. 14 45 NO FURTHER ENTRIES TH!S SHIFT. I TIME REVIEWER'S COMMENTS 14.04 Revwwod Log PB laaecs t 4 i 1 ) 1 4 d i i 4
) 19-Sep 96 2 a
l CHEMISTRY DEPARTMENT POLICY UPDATE 9/17/96 A. When procedures are being used that require equipment being placed 005, an example would be the Plant Vent monitor during sampling evolutions, thsn h the equipment shall not be declared back in service until the IV is completed. If the evolution is required on the ; back shift, thin notify the ANPS that you need support for an IV before you can declare, the equipment back in service. B. Sample labels will be provided in all of the labs. If a sample leaves your possession and ! will not be analyzed by you,1tlin a label should be filled out and attached to the sample
- container. Examples of such samples are as follows:
1 S/G Resin Samples, S/G DEQ's, Liquid Release Samples, etc. ' 1
~
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. ., , L J '
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l 1 CHEMISTRY Real Time Training Coach Report To: Kris Metzger' Report # 00002 l From: Jeff Heirmid ~ s - Date: 08/20/96 l
~~.__
I issue: On 8/12/96, a Unit 1 Post Accident Sampling System (P.A.S.S.) Operability Check was performed. A step within a step was not performed which caused the Unit 1 ) Containment Atmosphere Monitor to be out of service due to containment isolation valves being shut. The P.A.S.S procedure, which is required by Tech. Specs., did not have an IV step in it. Two technicians were involved; one received 3.5 days off, the other got a letter in his file. 4 Action: 8/13/96 -1030 Devin discussed latest " incident" with 3 chemistry technicians including: procedure compliance, attention to detail, actions to take when procedures need improving. Apparently, the Unit 1 PASS procedure has single steps that contain multiple actions, it does not have any 1.V. steps.
~1500 Dave Faulkner, the Chemistry Department Head, gave a stand down meeting '
concerning the Monday afternoon event. He discussed departmental policy, procedure compliance, attention to detall, independent verification and actions to take when procedures need to be improved. The Unit 1 and Unit 2 P.A.S.S. procedures have the highest priorities for Procedure Change Requests (PCRs). They will be thoroughly ri ' sed to avoid future confusion and they willinclude Independent Verifice.# requirements. If possible, I will coach the next P.A.S.S. Operability Check. Status: CLOSED cc: Tom Ware Devin Wooldridge Chemistry Training. Plan
/n/
/
Author: Divin Wooldridgs at USFPL830 Dato: 7/12/96 8:39 Priority: Normal R!ceipt Requested
*0: Dave Faulkner at USFPL800
- Bo Butler at USFPL800 CC: Russ Cox at USFPL800 CC: Dennis Harte at USFPL800 CC: Joel Burgess at USFPL800 CC: Ed Meyer at USFPL800 CC: Tom Ware
Subject:
Procedure Review Process
------------------------------------ Message Contents -------------------------------------
As you and I discussed, the Chem Dept is in need of a procedure review process for new and revised procedures (including guidelines). I am proceeding with implementation of the process that we discussed. The following are some details of the procedure review prior to implementation process that I am planning on coordinating:
- 1) new/ revised procedure or guideline comes to Dept Head for review and approval
- 2) Dept Head instructs individual sponsoring procedure / guideline to copy Devin (Trng) --
this will be the same copy of procedure which is sent to Information Services for word processing and same copy of , guideline which gets copied and distributed
- 3) Devin (Trng) will package procedure / guideline into a Procedure Bulletin package and deliver to Chem Supervisor responsible for coordinating training activities (supervisor to be determined)
- 4) Chemistry Supervisor responsible for coordinating training activities will ensure that the Procedure Bulletin gets distributed to the ' troops' and is returned by the due date (as determined by Chem Supervisor) ,
- 5) " troops" will be expected to review and route the Procedure Bulletin in a timely manner
- 6) once all Chem personnel have reviewed the Procedure Bulletin, it will be sent to/ collected by Devin (Trng), who will document and archive the completed sign-off sheets Note: While these steps are being taken, Devin (Trng) will be analyzing changes to determine training relevancy for Chemistry Techs.
It appears that in the upcoming months that there will be quite a few procedure changes coming. That means that initially there will be a lot of activity concerning Procedure Bulletins, but that activity should taper off over time. I believe the effort will be worthwhile because this process has many benefits for everyone involved. If you can think of anything that I forgot, please contact me at X3564 or E-Mail me. Devin i
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a p Inter-Office Correspondence lllllDL MGMT/PSL
, , Ltr. Bk. #96-102 To: Maint. Personnel cate: September 17,1996 From:
J. Marcheseg /g/ oepartment: Maintenance Manager
Subject:
M&TE (. Effective immediately, the M&TE storage areas will be locked at all times with access given
'n Chief Electricians, Foreman, and ' Supervisors ONLY. The Chiefs Foremen, and Supervisors e responsible for ensuring that all equipment is properly logged in and out when the areas are not being attended by M&TE personnel. This is a requirement of QI 12-R/PSL-2 and includes all shifts. Chief / Foremen / Supervisor access is currently provided by the keys which have been issued by each department. Checking in and out of M&TE is performed by the bar code computer system located in each facility. If the computer system is not available a manual check out log sheet is accessible near the computer station. If used, this log sheet must be filled out completely. All M&TE must be signed out to a NPWO, procedure, or similar document to ensure traceability from the instrument in the field back to NIST (National Institute of Standards and Technology). If you have any questions concerning this policy contact either Les Collins, Gary Edwards, or Tony Rossird.
This is mandatory, it is a procedural requirement and until "we" make the decision to revise / change our procedures and conduct our business differently. Your utmost cooperation in this matter is needed. JM:LC/dae b 6 f
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I q Dam ate m gl(b' l W d==d y; e/11/06 I i !
- 1. Toured both Control Rooms. Entered Unit Two through fan room. Fan room house ;
keeping is in good shape. NPS turnover in progress in Unit Two. Control room quiet, ; j and operators attentive to their duties.
' .i Observed Unit One control room Day / Peak shift turnover meeting. Information listed on
- each position's turnover sheet was reviewed during the meetmg. Meeting was businesslike with an opportunity for any questions to be addressed. The board operator maintained his. l
;. focus on his watch station. Annunciators were responded to as required. Housekeeping
- in both control rooms was very good.
l : } Performance Monitor: Lee Bearror I ) d
- 2. Toured Unit 1 RAB to familiarize a new employee with PSL [1.5 hours). Observed: !
- Housekeeping - Was excellent, did not observe trash other than in appropriate !
j containers. No oil or water was observed on floors or equipment. Protective l l clothing was properly stored. Did not observe clean and used clothing laying j. around step of pads as in the past. i } HP postings - Observed postings were properly posted at entrances to areas and at I l step off pads and barriers. (No in-progress jobs were observed.) ! } The few personnel encountered were wearing dosimetry properly. j Performance Monitor: Bruce Parks ~ i ! 3. An independent review of licensee event report (LER) 335/96-007, " Inadvertent Start of '
- the IB Emergency Diesel Generator During "B" Channel Containment Isolation Actuation Signal Testing Due to Procedural Inadequacy," dated July 8,1996 was conducted due to i indications of an operational deficiency that could affect nuclear safety. The review was
, conducted to evaluate the causes identified and corrective actions specified for an j inadvertent Emergency Diesel Generator (EDG) start.
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; 4. An independent review of the LER found that the report contains the information required j by 10CFR50.73 including: operating conditions before the event, a description of major
{ ! occurrences, personnel errors, corrective action taken and planned, and a narrative < { dem.iig;on of what occurred and its known causes. This review also verified that the LER l was submitted within the time limit (30 days) required by the 10CFR50.73. i This independent review found that appropriate generic and operability issues were I i identified. Additionally, the corrective actions included in the LER adequately address the 1 identified event causal factors. However, an additional event causal factor relating to prerequisite conditions for surveillance testing of the CIAS should be' addressed. 4 I. , . _ . . . . . , . ___ __ ._ _.. -
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o p Specifically, an inadvertent EDG start could occur due to completion of the EDG start actuation logic from under voltage circuit component or fuse failure concurrent with the CIAS surveillance. Verification of the bus voltage sensing circuit condition as a prerequisite t'o CIAS surveillance performance would help preclude an inadvertent EDG start due to component failure. A recommendation to include additional prerequisite conditions in the CIAS surveillance procedure will be included in a complete report of the event review, to be issued as part of the September 1996 QA monthly performance monitoring audit report. i Performance monitor: C.E. Norris ;
- 5. Monthly surveillance of calibration activities was conducted and three areas of i noncompliance to procedure were identified. QI 12-PR/PSL-2, paragraph 5.3.1.A requires that a calibration sticker be attached to each M&TE item. Contrary to this, item E-586 was found in the general population without a calibration sticker. QI 12-PR/PSL-2, !
paragraph 5.3.2 requires that the M&TE storage areas shall provide sufficient separation ; of the ready-to-use equipment (calibrated and restricted use) from other equipment 1 (rejected) to preclude inadvertent use. Contrary to this, item E-593 has a Reject sticker l on it, but was not separated to preclude use. Items E-647, E-253, and E-648/15 are all out of calibration, but remam in the general population available for use. QI 12-PR/PSL-2, paragraph 5.3.2.C requires security of the storage areas shall be maintained by a designated individual responsible for logging in and out all measuring and test equipment. In the absence of this individual, the storage areas shall be locked with access and logging controlled by the responsible supervisor. Contrary to this, this inspector observed three electricians and one I&C technician access the facility to obtain M&TE. Interviews with several electricians has revealed that all journeymen have the combination to access the M&TE facility. QC issued CR 96-2203 to document these discrepancies.
]
Performance Monitor: D. Gingras
- 6. Monitored the remo"al of asbestos material as per AP 0010504 R/6 while repairing a fire barrier under W/O 96017990 01. The Maintenance Services insulato was trained and certified in asbestos abatement, Title 2 of TSCA. The removal area was completely enveloped using the glove bag technique. All work was supervised by the FPL Asbestos !
Competent person. The removed material was double bagged, inspected by H.P., and then stored at the asbestos lay down area; all results were satisfactory. j Performance Monitor: R. Storms
- 7. In support of the IB Main Transformer repairs, inspected welds for the south tank support as detailed in PCM %132, CRN 6505; results satisfactory.
Also inspected socket welds per NPWO 8339 on line CW-374 (Circulating Water Pump); result were satisfactory. Performance Monitor: G. Ingram
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- 8. The current program for PC-2 items requiring field dedication lacks administrative and ,
maintenance procedural guidance. Confusion on acceptability of components which creates work delays. ) i i Example: after receipt inspection, dedication tags are applied to items listing remaining dedication inspections. 'Ihese inspection attributes are taken from the dedication packages ; critical characteristics matrix. Dedication tags list " Verify fit and function," however there
- is no accept / reject criteria provided.
QC is required via TS 10.1, paragraph 5.1.3 to install hold points for field dedications j these hold points are to read as follows: " Document as-found critical characteristics of the part" and "the part physically fits, no vibration etc." This parallels dedication package wording which states for fit and vibration, " Bearing properly fits when installed with no j' obvious clearance / installation problems and acceptable vibration and operation testing."
- No qualitative criteria is provided to QC for acceptance not for rejection. Thus the j dedication inspection provides no added benefit to the work process.
l Currently, during NPWO issuance, the entire dedication package is copied and placed in i PWOs requiring PC-2 parts so the foreman and journeyman can review. There are two j differing dedication format documents that may be issued. One form has signature steps for verification of attributes, one does not. Neither document lists who is responsible for
- signature; the foreman and journeyman are confused as to if these steps have been
- previously performed and whether the signatures are for QC or M/M. Neither AP t 0010432, Maintenance QI 11-PR/PSL-1, nor QC TS 10.1 describe the use of these
- dedication packages. Currently, there is no administrative procedure giving process l guidelines in the dedication process.
i The current process of PC-2 parts dedication, for all site disciplines, lacks procedural controls of dedication documents. Existing dedication documents have ambiguous requirements that do not provide acceptance criteria. QC issued CR 96-2202 to document the lack of a dedication process that is proceduralized for use by site personnel. i Performance Monitor: R. Hawley
- 9. Surveilled EM impleraentation of NPWO 2188 for testing of FCV-25-18; results
.. satisfactory. Reviewed six U-2 I&C NPWOs for paperwork closcout; results satisfactory. Performance Monitor: R. Brown
- 10. Conducted final visual inspections of conservator tank oil piping welds, under NPWO 8372 and PCM %132; welds were foun'd to be satisfactory.
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; Performance Monitor: B. Miller 4
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i 11. MOUNT VERNON - Replacement Steam Generator Progress Report ; RSG # 1 Completed all actions required to start the fitup. Installation of the heat shield is in progress, with fitup of the steam drum to heat exchanger scheduled for next ' week. l The weld prep on the steam drum shroud was modified to allow full root penetration. This ; job is complete. RSG # 2 Insulation has been installed on both the heat exchanger and steam drum. ; Miscellaneous / Common Items All QA records supporting the manufacture of the steam drum that are completed to date ; are in Cambridge. These records are part of the history docket and are being added to the - heat exchanger portion. The end result will be a seamless record, where the manufacturing location will not differentiate in the final record format. : Performance Monitor: Rick Weis 1 i 4 9 i i i I j O
p}u Collm .' M oTE d ' SEvanY EVEL CR NO. % ~ i. 2 Ob x o 3e un CONDITION I
- Ug*C" '" O *8 '" O g REPORT D' C N8' PAGE 1 &
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- s. CONDmONREPORTASSINEDTO:
COMMENI5 r" E O NP 700 REPORT O ROOTCAUSE ANALYSIS O INVES11 GATE & 00RRECT PLANTGENRAL MANAGER 4BCRRP DATE N /
<eC$ts ARE QA RECORDS WHEN CLOSED: PLEASE ENSURE ALL RESPONSES AND ATTACHMENTS ARE.
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CR# M -2.ZC3 A TACHMENT#1 M 2. Of Electrical measuring and test equipment (M&TE) facility is in violation of QI 12-2. Q.C. surveillance of the facility on 9-11-96 has identified the following discrepancies: 1.0112-2, Para 5.3.1.A states a calibration sticker is attached to each M&TE item. Contrary,E- 586 was found in the general population without a calibration sticker.
.2.Q112-2, Para 5.3.2 states the M&TE storage areas shall provide sufficient seperation of the ready-to-use equipment (calibrated and restricted use) from other equipment (rejected) to preclude inadvertent use. Contrary, E-593 has a Reject sticker on it,but was not properly seperated to preclude use.Further,E-647,E-253 and E-648/15 are out of calibration but stillin general population.
h 3.QI 12.2, Para 5.3.2.C states security of the storage area shall be maintained by a designated individual responsible for logging in and out all measuring and test
. equipment.in the absence of this individual, the storage areas shall be locked with access and logging controlled by the responsible supervisor. Contrary,this inspector observed three electricians and one l&C technician access the facility to obtain M&TE. Interviews with several electricians has revealed that all journeymen have the combination to access the M&TE facility.
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f - ROOT CAUSE EVALUATION LEVEL 3 INVESTIGATE AND CORRECT CRS 'A I. ANALYSIS OF THE PROBLEM / APPARENT CAUSE , A potential 10CFR21 notification regarding contaminated steel from DuBose Industrial Products
- was investigated for validation and use. The material was received at PSL on PO 94930-90023 in 2/8/94. The material is 1/4"x4'x8' steel plate, stock code 0030258-1.
The above steel was used in the following components /stmetures: 4 i Componen_tl Location Up_i1 P_W_Q Restraint CW-3000B-65 INTK/19/N-4/E-C 2 4155
- TCW-14-4B (VALVE) CCW/15/N-954/E-1726 1 6525 l
j (SEE CRN-036-196-6251 FOR LOCATION) ! l
. SUPPORT FOR WRSGL RCB 2 1610 !
I (SEE PCM 068-294, CRNS 068-294-5383, -5336, -5484, DWGS JPN-068-294-024, -025 & !
- FSK-M-530 FOR LOCATION, ATTACHED) l CRANE TEST WEIGHT LIFTING OUTDOOR (SOUTH 40) 00 3364 i APPARATUS l (SEE DWG JPN-JPSL-89-045-C-001 & WYATT JENKINS, X-4201 OF CONSTRUCTION j FOR LOCATION) i Contamination will not affect the structural integrity of the 1/4" steel plate. Therefore, no
[ operability concern exists with the condition noted above. 1 II. SPECIFIC CORRECTIVE ACTIONS
- Plant Health Physics shall take appropriate actions III. GENERIC ACTION (S) NECESSARY TO PREVENT RECURRENCE N/A l
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- v. S. A. Valdes omr. July 22,1996 St. Lucie Plant r== D.J. Denver ( w JPN/PSL Nuclear Engineering sw ST. LUCIE PLANT UNIT 2 2B Charging Pump Seal Laakage Evaluation JPN-PSL-SEMS-9tM51, Rev 0 Attached for your use is Engineering Evaluation JPN-PSL-SEMS-96-061 which was developed based on a verbal request of Operations and SCE.
Engineering was to evaluate the maximum potential fluid flow past the 2B Charging Pump seals during the 7/13/96 charging pump pacedng leak event. Based on an evaluation of personnel observations made during the 7/13/96 event. Engineering concludes that the maximum potentialleakage rate was less than 10 gpm (approximately 4.13xn). We conclude that NFK: notification was conservative but was not required. This finding is in agreement with the initial review made by Dave Stewart of SCE shortly aber the event. Please call me . t :' 2.
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- t 4 7 7276 should you have a concem or a question.
DJD/ G cc: C. Wood - SCE/PSL D. Stewart - SCE/PSL H. Johnson - OPS /PSL J. Scarola - PGWPSL G. McKenzie - JPN/PSL J. Fulford - OST/PSL E. Weinkam - LIC/PSL p
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