ML20080S326
| ML20080S326 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/13/1983 |
| From: | Ellis J Citizens Association for Sound Energy |
| To: | Atomic Safety and Licensing Board Panel |
| Shared Package | |
| ML20080S315 | List: |
| References | |
| NUDOCS 8310180342 | |
| Download: ML20080S326 (497) | |
Text
{{#Wiki_filter:m 10/13/83 UNITED STATES OF AMERICA HUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of APPLICATION OF TEXAS UTILITIES I Docket Nos. 50-445 I GENERATING COMPANY, ET AL. FOR I and 50-446 - l AN OPERATING LICENSE W COMANCHE PEAK STEAM ELECTRIC I STATION UNITS #1 AND #2
'(CPSES) g CASE'S (1) MOTION TO ADD A NEW CONTENTION, (2)MOTIONFORDISCOVERY,AND (3) 0FFER OF PROOF Pursuant to 10 CFR 2.'43(a) and (3) and 10 CFR 2.714, CASE (Citizens Association for Sound Energy), Intervenor herein, hereby files this, its (1) Motion to Add a New Contention, (2) Motion for Discovery, and (3) Offer of Proof.
CASE moves that the Board accept as a new contention the following: PROPOSED CONTENTION 26 The Licensing Board cannot make the required findings under 10 CFR 50.57(a) and the Applicants cannot be granted an operating license for Comanche Peak Steam Electric 3tation (CPSES), Units 1 and E, I for the following reasons:
- 1. The Hot Functional Test (HFT) was deficient in that major com-l ponents or items of equipment were not installed at the time of l the test.
- 2. Significant modifications have been made or are contemplated which require an additional Hot Functional Test (HFT) with all finalized components and equipment in place in order to validate the design /
construction process. l l l l 8310180342 831013 {DRADOCK05000g
PROPOSED CONTENTION 26 (continued):
- 3. Applicants do not intend to check or monitor some of the major components or items of equipment which were not installed at the '
time of the Hot Functional Test (HFT) until " heat-up to hot stand-by" or "during power ascension." Thus, they have not proved that their corrective action is sufficient to assure safe operation, which must be proved prior to fuel loed and the granting of an operating license.
- 4. The Licensing Board should order or request a complete reinspection of all components, equipment, welding, etc. (i.e., everything) because:
(a) neither Applicants nor the NRC Region IV Staff noticed that major components or items of equipment were not installed prior to the Hot Functional Test (HFT); (b) the HFT considered only nonnal operating conditions and did not include consideration of accident conditions such as Loss-of-Coolant Accidents (LOCA), earthquakes, etc.; the extent and magnitude of the problems in construction and/or desiga which were discovered during the HFT decreases the likelihood that CPSES could be operated successfully under accident conditions; and (c) the willingness of both Applicants and the NRC Region IV Staff to accept HFT results which are deficient renders it impossible for the Licensing Board to rely on test'results to assure that CPSES has been built and can be operated in such a manner that the public health and safety will not be jeopardized.
- 5. Problems in construction and/or design revealed by the Hot Functional Test (HFT) and related tests, as well as containment test , leak rate tests, and other tests undertaken in preparation for fuel load are so extensive and of such magnitude that they must be corrected before fuel load can be allowed.
- 6. In order for the health and safety of the public to be assured, Applicants must correct these problems in construction and/or design, following which they must run additional test (s), including a Hot Functional Test (HFT), until such time as the HFT and other tests can be run successfully with all finalized components or equipment in place.
- 7. Neither the NRC Staff nor the Applicants have informed the Licensing Board of the true extent and magnitude of these problems in construction and/or design, in direct violation of the Board's explicit and express directives to all parties to keep the Board informed of significant or potentially significant matters relating to these proceedings.
4 PROPOSED CONTENTION 26 (continued):
- 8. For the preceding reasons, it is necessary for the Licensing Board itself to closely monitor the successful completion of such tests and reinspections, rather than relying upon the NRC Staff to monitor such tests and reinspections (as a condition for licensing or otherwise).
- 9. The lack of candor by both Applicants and the NRC Region IV Staff calls into question their credibility and/or competence. Because of this, the Licensing Board should recognize that the evaluations of these tests by Applicants and/or NRC Staff are less than complete and accurate, and the Board should take this into consideration in the weight given to testimony by both Applicants and NRC Staff and in mak'ng its decisions in these proceedings.
- 10. Separate tests should be required for Unit 2, rather than relying on tests perfonned for Unit 1, since the tests already conducted reveal prob'. ems in construction and/or design which are so exten-sive and of such magnitude that the tests for Unit 1 cannat be relied upon to assure successful tests for Unit 2.
- 11. For the reasons stated in the preceding, the Licensing Board should order or request a complete reinspection of all components, equipment, welding, etc. (i.e., everything) as discussed in item 3 preceding for Unit 2 as well as for Unit 1.
REGULATIONS GOVERNING NEW CONTENTIONS The NRC regulatiors governing new contentions are those which apply to intervention, as set forth in 10 CFR 2.714(a)(1), which states that the petition and/or request should be granted based upon a balancing of the follow-ing factors: (i) good cause, if any, for failure to file on time; (ii) the availability of other means whereby the petitioner's interest will be protected; ('iii) the extent to which the petitioner's participation may rosonably be expected to assist in developing a sound record; (iv) the extent to which the petitioner's interest will be represented by existing parties; and (v) the extent
REGULATIONS GOVERNING NEW CONTENTIONS (continued): to which the petitioner's participation will broaden the issues or delay the proceeding. (See discussion at Tr. 7688-7715 regarding late-filed contentions.) Obviously, there are no other means available whereby CASE's interest will be protected; these operating license proceedings are the only forum available in this regard. Equally obvious, CASE's interest will not be represented by existing parties in these proceedings; CASE is the only party taking cn adversarial- position in opposition to Applicants' receiving an operating license. As shall be demonstrated in the following, good cause exists for CASE's not having filed this contention prior to this time. Further, litigation of the issues raised in this contention are of vital importance to the development of a sound record in these proceedings and is necessary in order for the Board to make an informed, reasoned decision based on a sufficient factual record. In addition, although further hearings will be necessitated by this contention regarding specific issues, those issues flow, in part, from CASE's QA/QC Contention 5 (and in m:ay instances cou d probably be covered under Contention 5); the other issues raised have W to do with items of major significance, based on new information which shculd have been provided to the Board by Applicants and/or the NRC Staff. 10 CFR 2.743(a) and (e) also apply here and state, in part:
- "Every party to a proceeding shall have the right to present such oral or documentary evidence and rebuttal evidence and conduct such cross-examination as may be required for full and true disclosure of the '
facts."
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i GOOD CAUSE EXISTS FOR CASE'S 'NOT HAVING FILED THIS CONTENTION PRIOR TO THIS TIME It was impossible for CASE to have filed this contentien prior to this time , because we did not have access to the new and significant infonnation discussed herein prior to this time. Further, some of the information did not exist previously since it apparently has to de with items after the last hearing (s). It was only during discovery conducted by CASE as an Intervenor in the Dallas Power & Light rate hearings that this new information came to CASE's attention.
~
By way of background, CASE has intervened in all Dallas _ Power & Light rate hearings since 1974. It was CASE's concern at that time regarding the Comanche Feak nu:: lear plant s:hich led to our intervention in rate cases, and we have developed expertise regarding the costs of Comanche Peak in the almost ten years since we began that intervention. The amount of time and resources devoted to'such intervention in rate cases is very small compared to the amount of time and resenrces necessary to intervene in these operating license proceedinp. Initially, CASE had not planned to intervene.in the Dallas Power & Light ;
- rate case which was litigated October 3-7, 1983, because of our already heavy work load in these proceedings. However, since CASE is perhaps the most knowledgeable organization at tnis time regarding the Comanche Peak plant
. and its associr,ted costs and the reasons for them, CASE Board members h:. Barbara Boltz and Dr. David Boltz intervened on a very limited casts in [ the rate hearings, while other CASE members (including CASE President Juanita
- Ellis) continued to devote their efforts to these operating license prcceedings.
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I 6-l GOOD CAUSE EXISTS (continued): 1 Mrs. Ellis did assist Dr. and Mrs. Boltz in attempting to obtain documents
! -- documents which we believed were significant not only for the rate hearings
- but for these operating license hearings as well -- when Dallas Power & Light, 1
which is siso one of the owners of Conanche Peak and one of the Applicants 4 in these operating license proceedings, attenpted to prevent CASE from obtain-ing the documents at first, then to prevent us from ottaining them except under j a protective order which would have made it impossible for us to call the docu-j ments to the attention of the Licensing Board in these proceedings. (See attached copy of CASE's 9/24/83 Supplementary Motion to Compel Applicant to Provide Photocopies of Doceents Being Made Available to CASE at CPSES in l Response to CASE's RFI's Nos. 6-12 and 20; Examiner's Order Ruling on DP&L's I Objections to CASE's RFI's dated August 22, 1983, copy attached; and Examiner's
?
i Order Concerning Motions Discussed at Prehearing Conference Held September 29,
' 1983, dated September 29, 1983, alsoattached.)
It was, in fact, Dallas Power & Light's (and, we asstane, TUGC0's) extreme l reluctance and objections to this information's being brought to the attention l of the Licensing Board in these licensing hearings that first kindled the interest of CASE President Juanita Ellis in the documents being fought over. It has been our experience in the past when dealing with the Applicants (both in the rate hearings and in the operating license hearings) that if they over-react i and object too strenuously, there is usually some very significant and important l information which they do not want brought out. This was again the case with the particular documents in question, which are of great significance and are i i i I l
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' ~~ _7_ GOOD CAUSE EXISTS (continued): extremely important in the operating license proceedings, as well as the DP&L rate hearings. Applicantsl fought long and hard, although unsuccessfully, riot only to avoid reporting the significant and extensive problems discovered during
. testing undertaken in preparation for fuel load to the Licensing Board in these proceedings. Further, they attempted to keep CASE fmm calling these vitally important matters to the attention of the Licensins; Board. As stated in CASE's 9/24/83 Supplementary Motion to Compel in the rate hearings (copy attached), pages 5 and 6:
"It should be noted that CASE has attempted to keep separatt:d the operat-ing license hearings and the DP&L rate hearings for the most part, and we had planned to introduce into evidence and question Applicant's wit-nesses regarding only a handful of-documents from the operating license hearings. However, Applicant's continual allegations that CASE only wants documents in the DP&L rate hearings in order to use them in the ,
operating license hearing- for Comanche Peak forces us to b' ring these matters to the Hearing Examiner's attention.
" Applicant would have CASE gagged from reporting any potentially sig-nificant matters discovered during the rate hearings -- gagged from reporting _them to the very agency (the U. S. Nuclear Regulatory Com-mission) which has been mandated by Congress to protect the ptblic health and safety and to see that nuclear power plants are designed and constructed in such a manner that the public health and safety will not be jeopardized." (Emphasis in. the original.)
" CASE submits that Applicant's efforts in this regard are for one purpose and one pugose only -- to prot.ect Applicant's from having to deal with deficiencies in management for which they should have to answer in these t (the rate) proceedings, while at the same time assuring that they will not have to deal with those deficiencies in the NRC operating license hearings for Comanche Peak." (Emphasis in the original.)
"To place CASE in such an untenable position is bad enough. However, I Since Dallas Power & Light is also one of the owners of Comanche Peak and one of the Applicants in the operating license proceedings, as well as being the Applicant for a rate increase in the' Dallas Power & Light rate hearings, we will use the term " Applicants" throughout the remainder of this discussion interchangeably.
. . -g-GOOD CAUSE EXISTS (continued):
to attempt to make the PUC a party to such unnecessary, illogical, and perhaps even illegal withholding of information from the NRC is even worse, and CASE urges that the Hearing Examiner and the PUC riot fall for Applicant's ploy and thus become e party to such a questionable and perhaps even illegal maneuver.
" CASE simply cannot both comply with the proposed Protective Order and at the same time fulfill its obligations as an Intervenor in the operating licensing hearings for Comanche Peak. It is grossly unfair to ask that we attempt to do so. Further, Applicant has not and cannot show adequate grounds for a protective order, because no such grounds exist." (Emphases in the original.)'
. . . In conclusion, CASE should not be penalized and placed in such an untenable position because we are concerned not only with rate-setting but also with public health and safety. There are two distinct and separate forums for expressing these concerns--the PUC for rate-setting and the NRC for public health and safety. The PUC should not be a party to assist-ing the Applicant to hide any safety-related problems which may be un-covered durirg discovery in these proceedings--problems which (if uncovered) should properly be called to the attention of the Atomic Safety and Licensing Board of the Nuclear Regulatory Commission in order to safeguard the public health and safety. Nor she'lld the public be.kept from knowing how much any repairs, redesign, modifications, reconstruction, etc. are costing them."
CASE submits that Applicants' blatant and frenzied attempts to hide these documents from the Licensing BMrd clearly demonstrates their total contempt for the Board and these proceedings. Further, their unsuccessful efforts in this regard demonstrate more clearly than anything else CASE could say that these documents and infonnation are relevant, material, and of vital importance l in these proceedings2 , 2 In the interest of time, money, and the size of the record in these proceed-ings, CASE is submitting only a small fraction of the documents we received on discovery in the rate hearings -- this small fraction was itself only a very small fraction of the documents regarding deficiencies discovered during tests undertaken in preparation for fuel load, i CASE will bring the entire two punchlists which we received on discovery l to the operating license hearings beginning October 17, 1983, and we urge L the Board to examine these punchlists at that time so that they can see firsthand the magnituue and extent of these problems in construction and/cr design. i
9-GOOD CAUSE EXISTS (continued): _ Testimony in these proceedings by both Applicants and the NRC Staff regarding the magnitude and extent of problems in' construction and/or design at Comanche Peak has been misleading. CASE has already addressed in some detail the lack of credibility and/or competence of both Applicants' and NRC Staff's witnesses in these proceedings (see especially pages XXVII -1 through
-51 and pages XXX - 24 through -30 of CASE's 8/22/83 Proposed Findings of Fact and Conclusions of Law (Walsh/Doyle Allegations)). In addition, we call the Board's attention to the following which, along with other mislead-ing statements by Applicants and the NRC Staff, is one of the reasons for CASE's not having filed this contention prior to this time.
Inspection Report 50-445/83-08, under cover letter of April 29, 1983, included a discussion of " Hot Functional Test" (pages 5-7) and " Plant Status" (page 8'). During the May 19, 1983, hearings, CASE asked some specific ques-tions regarding this document (which was bound into the record following Tr. page7000). Our questions had to do with'an item on page 6 of the report, wherein it was mentioned briefly regarding the Hot Functional Test that:
"Several problem areas have been encountered. The major areas are:
"a. Erratic behavior of RCP seal flows "b. Thermal expansion l "c. Letdown orifice size" CASE asked some questions primarily regarding the problem with the thermal expansion test (see full discussion at Tr. 7000-7004), then (Tr.
7004): l l
_ 10 - GOODCAUSEEXISTS(continued):
"MS. ELLIS: Are you aware of any areas that are invnived in this which have to do with any of the things that we have been discussing or that CASE has raised as issues in these proceedings?" (Emphasis added.)
" WITNESS TAY'_0R: No, ma'am."
However, as demnstrated in the following more detailed discussion of the problerts in construction and/or design which were brought to light during the Hot Functional Test, the pmblems with thermal expansion and other problem areas in the Hot Functional Test have very much to do with aspects cf CASE's Contention 5, including but not limited to concerns relating to the Walsh/Doyle allegations, pipe whip restraints with which CASE witness Charles Atchison was very much concerned, and the pervasive failure of Applicants' quality assurance / quality control program to detect these problems prior to the Hot Functional Test and the NRC Region IV Staff's lack of adequate oversight w'nich allowed such pmblems to develop to this stage. Yet there was nothing in the wording of Inspection Report 83-08 to indicate the magnitude of the problems encountered. In fact, it is stated f (page 8):
"6. Plant Status l . . . No violations or deviations were identified"
. . . even though there were problems discovered during the Hot Functional Test which were of major concern and significance, some of which should undoubtedly have been reported under 10 CFR 50.500s).
In addition, there have been no indkations in previous testimony by the NRC Staff or in other NRC Staff documents to indicate the magnitude and extent of problems in construction and/or design which have been discovered ! at Comanche Peak. 1
- 11 _
GOOD CAUSE EXISTS (continued): For example, Inspection Report 50-445/83-26, under cover letter of June 15,1983, stated (pa52 6) :
"5. Hot Functional Test "The licensee completed the last evolution of the hot functional test (HFT) on May 27, 1983. This evolution required cooldown to ambient condition and demonstration of plant control from outside of the contiol room. The plant is presently in a solid water condition and the licensee is proceding with pmoperational testing. The tests that are scheduled do not require the plant to be at elevated pressures and temperatures.
"No violation or deviations were identified."
This gives the impression that everything is going along smoothly with the Hot Functional Tes,t and that there are no significant problems. And the recent memorandum for files prepared by NRC Staff witness David Rohrer documenting a conversation between Mr. Rohrer and Judge Bloch on September 9,1983, stated (see 9/23/83 Memorandum for EPB Files, attached to cover letter to the Board from the NRC Staff dated 9/29/83):
. . . the . inspector infonned me that one of the reasons for this potential for slippage of the fuel load date was due to minor diffi-culties experienced during hot functional testing. . ." TmDases added.) [3/
It was not until recently that a few indications began to creep into NRC Region IV Inspection Reports that there might be more extensive problems with the Hot functional Tests than had been previously indicated. 2 CASE is not certain whether or not the Board has received a copy of this Inspection Report. If not, we assume that it has accers to it, or C'.SE will pmvide a copy should the Board desire. 3 It is CASE's reco',lection that when Judge Bloch reported the conversation to the parties, it was indicated tLit the extent of the problems experienced during the Hot Functional Test was somewhat greater than " minor difficuities." However, we do not at this time recall the exact wording.
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GOOD CAUSE EXISTS (continued): Inspection Report 50-445/83-34,50-446/83-18, which was fomarded to the Board by the NRC Staff Counsel under cover letter of September 26, 1983 (as being applicable to an allegation that the issuance of Nonconfonnance Reports (NCR's) had been affected by the dismissal of Mr. Atchison and alle-gatior relating to the reactor vessel outer wall) stated (page 5):
"The SRIO (Senior Resident Inspector-operations) reviewed the HFT log for any notation on the shield wall / reactor. vessel interface. There were no entries related to this specific subject in the log. There was a notatien that PT-45-06 ' Containment. Ventilation' failed tc meet its acceptance criteria because the following areas were too hot (thermally):
"(1) All vessel supports
"(2) Neutron Instrument Detector Wells
"( 3) Pressurizer Room
"(4) All Steam Generator Compartments" (Emphasesadded.)
This will be discussed in more detail in the following. And Inspection Report 50-445/83-36, under cover letter of September 27, 1983 (released by the Applicants with a news release on October 7, received by CASE on 10/12/83) stated regarding walkdowns by the NRC inspector (operations) (pages 4 and 5):
"The NRC inspector noted the following discrepancies and incomplete items during the walkdowns:
"a. Component Cooling Water System
"(1) The following pipes have not been completed:"
(lists 18 pipes)
" Suction and discharge lines to CCW drain tank pumps 01 and 02.
"This item is considered open. (8336-01) 4 n
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13 l 1 S GOODCNJSEEXIST_S.(continued):
"(2) The motors have been removed from CCW drain tank punps 01 and 02. j "This item is considered open. (8336-02)
"b. Containment Spray System
"(1) Check valve 1CT-145 internal has been removed.
"This item is considered open. (8336-03)
"(2) The following motor operated valves hve not been completed:" ,
(lists 2 valves)
"This iten is considered open. (8336-04)
"c. Chemical and Volume Control Systam
"(1) The following air operated valve limit switches have not been l completed:"
(lists 2 valves limit switches)
"(2) The following remote valve operators are not complete:"
(lists 13 remote valve operators)
"This ftem is considered open. (8336-06)
"While performing the walkdown of the component cooling water s i
the NRC inspector observed that the residual heat removal (RHR)ystem, pump 01 had been removeo. l "This item will be considered an open item in addition to the two open i items (8332 04 and 8332-05) noted in NRC Ir,spection Report 50-445/8332 l for the residual heat removal heat system.
"This item is considered open. (8336-07) l "These items (8336-01 through 8336-07) will remain open pending:
" Review of ' find (sic) as-built' flow diagrams against identified discrepancies.
" Completion of identified incomplete items.
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_ 14 - GOODCAUSEEXISTS(continued):
"The NRC inspector observed that numerous valves and instruments have not been marked with permantat identification tags. This itera was identified as Open Item 8332-10 in NRC Inspection Report 50-445/E332.
"This item will remain open pending completion of permanent tagging."
Thus, there is good cause for CASE's not having filed this contention prior to this time: (1) CASE dirnot have access to the new and significant information discussed herein prior to this time; (2) Some of the information did not exist previously and apparently has to do with items which were not knnwn until after the last hearing (s); (3) The infomation was not actually in CASE's hands until September 30, 1983, after 4:00 P.M.; (4) The infomation was obtained in regard to CASE's intervention in the Dallas Power & Light rate hearings and was discovered during CASE's discovery in that regard, for use in the rate hearings; (5) Applicants sought to hide this information from the Licensing Board in these proceedings and made it as difficult as possible for CASE t~o obtain; (6) Testimony in these proceedings by both Applicants and the NRC Staff regarding the magnitude and extent of prcblems in construction and design at Comanche Peak has been misleading; (7) Although CASE has been working diligently to review, analyze, and prepue the documents received ever since their receipt, this is a mamoth undertaking which was impossible to achieve
. ;y _
GOOD CAUSE EXISTS (continued): (7) (continued): prior to this time (especially in light of the Board's directives 4 to present evidence in a controlled, organized fashion ). DISCUSSION OF SPECIFIC PROBLEM AREAS AND DOCUMENTATION -- 0FFER OF PROOF As part of discovery in the Dallas Power & Light rate hearings, CASE received specific docunents, as well as answers to our interrogatories. We submit herewith as attachments relevant and material docunents selected from those docunents and answers, as an .0ffer of Proof to support our Proposed New Contention. These documents consist primarily of the following general categories: (1) Two lists showing all systems at Comanche Peak which have and have not been turned over to operations; (2) Documents relating to Hot Functional Tests and other tests under-taken in preparation for fuel load, including Test Deficiency Reports (TDR's); (3) Copies of a computerized " Master System Punchlist," Volumes I 4 Board's 8/15/83 Memorandum and Order (Motion to Supplement and Correct Record), page 1.
SPECIFIC PROBLEMS (continued): and II' May 25, 1983, consisting of 2469 pages with approximately 8 items per page = 19,752 items (selected pages only are attached); (4) Copies of a computerized " Master Data System" punchlist, 9/23/83, which was represented to ~ CASE during discovery in the rate hearings as consisting of open items which had not'been closed out5 , consist-ing of 1702 pages with approximately 7 items per page = 11,914 items (we are attaching selected pages only); and (5) Brief portions of the transcript of the Dallas Facer & Light rate hearings pertaining to specific problem areas discussed.
'*e have not yet obtained certifications of authenticity of these documents; however, we believe that we will be able to obtain stipulations or admissions from Applicants regarding their authenticity (and we are so requesting by letter to Applicants being sent at the same time as this pleading). We did not want to delay getting this pleading or these documents into the hands of the Board and parties, especially since we plan to also use some of the documents for cross-examination in the hearings beginning October 17, 1983.
5 However, in the Dallas Power & Light rate hearings, Applicant's witness Michael D. Spence, President of TUGC0 (and soon-to-be President of the Generating Division of Texas Utilities and Electric Company under the new organization), in discussing an item from the punchlist (CASE Exhibit
,865 attached, Main Steam System, page 281, item 0477S), stated that:
"By and large, I would suspect that most of the items on here are open, but some may have been closed in the data base and not updated. This one indicates it has been repaired." ( P. 153-154, Transcript portions of DP&L rate hearings,10/3/83, copy attached.)
_ 17 _ SPECIFIC PROBl. EMS,(continued): S Listing of all systems at Comanche Peak which have and have not been turned over to operations In the Dallas Power & Light rate heariags, CASE received answers to the following interrogatories:
"2. Please give a complete, detailed listing of all systems at Comanche Peak which have not yet been turned over to operations.
"3. In regard to the systems referred to in question No. 2, please provide the current scheduled tstget date(s) for the turn-over of each system which has not yet been turned over to operations.
"4. Please give a complete, detailed listing of all systems at Comanche Peak which have been turned over to operations.
"5. In regard to the systems referred to in question No. 4, please provide the date(s) that each system was turned over to operations."
The answers we received from Dallas Power & Light are attached as CASE Exhibits 854 (answers to questions 2 and 3) and 855 (answers to questions 4 and 5). During the DP&L rate hearings, Applicant's witness' Michael D. Spence, President of TUGC0 (and soon-to-be Prasident of the Generating Division of Texas Utilities and Electric Company under the new organization) was asked some specific questions regarding those matters. (See Tr'.134-140, DP&L rate hearings,10/3/83, copy attached.) (BY DR. BOLTZ) "Q: Could you please briefly describe what an a'cceptance test is? (BY WITNESS SPENCE) "A: . . . An acceptance test is one form of test that we are perfon..ing at Comanche Peak. Th> other type of test is a pre-operational test. . . An acceptance test is the kind of test that we would normally perfonn on components or systems within a non-nuclear, a fossil-typa power plant.
SPECIFICPROBLEMS(continued): Qsting of all systems which have and have not been turned over to operations (cont.):
"And this means that the individual components and their performance would be verified.as to their operation, and then, the system would be placed into service to provide initial system operation.
"There are no ' formal verbatim procedures required by NRC regulations to perform an acceptance test, as they are required on a pre-operational test of a safety-ro3ated system. . . Mandatory plcnt testing is not required prior to initial plant operation for those systems that require only acceptance tests.
"Q: Arg acceptance tests done only on turned over items or turned over systems?
"A: Yes, by definition, if a system has not been turned over from construction to startup into operations, then startup in oper6tions i can't test them. They don't have control of it.
"Q: Could you please briefly explain what the tenn turnover means?
"A: Yes, sir. A turnover takes place when a system or a subsystem within the plant has essentially completed its construction phase and construction turns the responsibility for that system over to startup in operations.
"Q: Let's assume it's a system work done by Brown & Root and they ~ complete it. So when they turn it over they give it to TUGCO. Is that correct?
"A: That's correct.
"Q: Does this mean, then, that once it's turned over that all construction is finished on that particular piece of hardware or system?
"A: No. There may be a punch list on it, and after the particular test that's required for that system, whether it be a pre-operational test or acceptance test, has been performed, that test may identify additional construction work that needs to be done. That's the reason you do the test - is to validate that system's performance in accordance with design specifications. . .
" Turnover takes place when Construction passes a system to Operations and says, 'Here. __We built it according to specifications. It is now ready for you to test and to operate.' Occasionally, Operations will
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SPECIFICPROBLEMS(continued): Listing of all systems which have and have not been turned over to operations (cont.): say, 'No, we're not ready to turn it over because there is an adjust-ment that we would like you to make or modifications we want you to make before we take the responsibilit.y for the system, because we don't have the capability to modify the constructionc That's your job, not ours.' And I used in my example maybe the accessibility of the valve in a piping system. Once that has been taken care of to TUGCO's satisfaction, they accept the system as being turned over to them and they begin their tests, whether it's a pre-operational test or an acceptance test, as the case may be, depending on the system. . .
"Q: Okay. I guess my concern was is turnovu an economic term as well as an engineering one? . . .
"A: No, it is not an economic tem. It is a technical tenn used in the~~ .
progression and the statusing of the physical develo) ment of the project. It was one among a number of tracking mechanisms we lave to track progress. The fact that we have turned over 90 percent of the systems from Constructior. to Operations indicates the approaching completeness of the construction process, as an example, as I testified to in my direct testimony " (Emphases added.') One important aspect of the preceding testimony is that it is in direct contradiction to testimony in the operating license hearings regarding the Walsh/Doyle allegations. One of the continuing premises advanced by Applicants has been that it's not fair for CASE to say that a particular pipe support is unstable (for example), because Applicants are not really, really through with it. The NRC Special Inspection Team (SIT) went to great lengths to
" prove" that the decwings submitted by Jack Doyle in his Deposition / Testimony (CA'SE Exhibit 669B) and the pipe supports identified by Messrs. Walsh and Doyle were preliminary and only in steps (4) and (5) of a nine-point procedure listed by the SIT. (SIT Report, NRC Staff Exhibit 207, pages 14-16.) However, the sworn testimony of the President of TUGC0 in the DP&L rate hearings clearly
SPECIFIC PROBLEMS (continued): Listing of all systems which have and have not been turned over to operations (cont.); indicates that this is act the case. We call the Board's attention specifically to CCE Exhibit 855 attached, the listing of all systems at Comanche Peak which have been turned'over to Operations. Messrs. Walsh and Doyle worked on the following systems (among others): SYSTEM DESCRIPTION ACCEPTED DATE i- RESIDUAL HEAT REMOVAL 29 JAN 82 1-4801 t,u , ' ENT SPRAY SYSTEM 09 NOV 81 1-3702 AUXILIARY r. 'TER SYSTEM 02 DEC 81 1-3703 AUXILI ARY FEEDWATER SYSTEM 15 DEC 81 1-2802 STEAM GENERATOR FEEDWATER SYSTEM 13 JUL 82 1-2801 FEED WATER 18 SEP 81 To be even more specific, consider pipe support RH-1-00E-008-S22K (CASE Exhibit 669B, page 13CC). This support is part of the residual heat removal system, which was turned over to operations on January '29,1982, well before Messrs. Walsh and Doyle quit at Ccmanche Peak. As a matter of fact, most of the supports contained in CASE Exhibit 669B (Attachment to Doyle Deposition / Testimony) had already been turned over to Op3 rations, according to the documents and testimony in the DP&L rate hearings. This again calls into question the credibility and/or competence of Applicants' witnesses and NRC Staff SIT witnesses in these proceedings. Further, it raises such questions in this regard that the Board should order Applicants to have Mr. Spence (President of TUGCO) available for cross-examination during hearings on the matters discussed herein.
. , SPECIFIC PROBLEMS (continued):
Listing of all systems which have and have not been turned over to operations (cont.) From the testimony in the DP&L rate hearings, it appears that the schedule for fuel load is based on when systems are turned over to operations. If proper calculations have not been made prior to such turn-over (for instance, ! regarding the suoports in CASE Exhibit 669B), does this mean that testing has been done without calculations having been performed? Or that Applicants
- intend to load fuel without having done the proper calculations?
Clearly, the preceding raises a number of questions -- questions which should be answered before Applicants are granted an operating license or allowed to load fuel, i 1 l
SPECIFIC PROBLEMS (continued): Listing of all systems which have and have opt been turned over to operations (cont.) Another aspect of this has to do with the use of proper guidelines at Comanche Peak regarding the QA/QC program. During the September 1982 hearings, Applicants' witness Mr. Tolson informed the Board that the construction phase used different guidelines than were used in the operations phase (Tr. 4496). And in another instance, when CASE attempted to have admitted into evidence CASE Exhibit 690, the 1974 edition of ANSI N45.2.1.1 (referenced in the FSAR at 17.2-2), it was concluded in an off-the-record discussion with Applicants that the supports in question were not covered by the 1974 Edition of ANSI N45.2.ll, but rather by the May 1973 Draft Edition, which Applicants submitted as Applicants' Exhibit 148. (CASE discovered that Applicants' Exhibit 148 was incomplete, and it was supplemented by Applicants and bound into the record as an Addition to Applicants' Exhibit 14E, following Tr. 7014.) CASE has not attempted to evaluate whether there are other differences in documents used for construction as opposed to operations. However, it has been demonstrated during the disc 0ssions, briefs, and testimony regard-ing the issue of Loss-of-Coolant Accidents (LOCA) and the ASME Code that which Codes and geidelines are used can be an important factor. It would theretcre seem prudent to require Applicants to make such an evaluation in these proceedings, with appropriate follow-up action if necessary, in order to prove what steps actually are taken. l
SPECIFIC PROBLEMS (continued): General It. formation Regarding Tests , The Hot Functional Test (HFT) is discussed in Item 18 of the information CASE requested in the DP&L rate hearings (CASE Exhibit 858 attached). It is listed as 1CP-PT-55-02. The last four numbers of the HFT and other tests are shown where applicable under the column "PT-AT" (which we assume means Propera-tional Test-Acceptance Test) on the Master System Punchlist (see CASE Exhibit 864 attached) and the Master Data System punchlist (see CASE Exhibit 865 attached). The various Tab numbers designate various elements of the Test, generally the same as those shown on the second page of CASE Exhibit 858 attached under Volume I: Tab I - Test Summary Report Tab II - Test Procedure
~
Tab III - Test Procedure Deviations Tab IV - Test Deficiency Reports (or TDR's) Tab V - Supporting Documentation i fab VI - Chronological Test Log Tab VII - Outstanding Items The various preoperational and acceptance tests which were performed during the Hot Functional Test are shown on the fifth and sixth pages of CASE Exhibit 858 attachea. Of these 27 different tests, CASE is attaching information from only 5 of them:
-,m,,, ,
. o SPECIFIC PROBLEMS (continued): General Information Regarding Tests (' continued): PT-34-02 S tea Generator Safety and Relief Valves (CASE Exhibit 862) PT-37-03 Auxiliary Feedwater Turbine-Driven Pump (CASE Exhibit 856) PT-45-06 Containment and Pump Room Cooler Temperature Test (CASE Exhibit 857) PT-5 5-09 Reactor Coolant Pump Test (CASE Exhibit 861) PT-55-11 Thermal Expansion (CASE Exhibit 860) We are also att ching information on the_ following tests: PT-55-02 Hot Functional Test (CASE Exhibit 858) XCP-PT-07-01 Control Room Heating & Ventilation System Performance
~(CASE Exhibit 859)
PT-75-02 Containment Integrated Leak Rate Test (CASE Exhibit 863) As an indication of the extent of the information regarding these tests, we will take just one of them as an example -- PT-55-ll, Thermal Expansion. There were 111 binders with raw test data plus two large volumes (approximately 3 inches thick each) which contained Test Deficiency Reports (TDR's); there were 420 TDR's, many of which have multiple items identified. Punchlists information regarding the punchlists has already been provided on pages 15-16 in this pleading. In addition, we invite the Board's attention to pages 17 and 18 of Insprction Report 50-445/83-23 (the NRC's inspection of the Fuel Building) where further details are given regarding punchlists. Apparently there are three punchlists: the construction punchlict, the completions punchlist, and the master punchlist. From the descriptions given in the I&E Report, we believe that the documents CASE received, and excerpts of which
.o .
SPECIFIC PROBLEMS (continued): Punchlists (continued): are attached, are the completions punchlist (CASE Exhibit 865, marked " Master Data System") and the master punchlist (CASE Exhibit 864, marked " Master System Punchlist"); however, we are not absolutely certain of this at this time. I&E Report 83-23 describes these punchlists as follows:
"The construction punchlist consists of outstanding construction items normally generated on a roon, or outside area basis. Work in these areas is performed in accordance with normal constructilin procedures with QA/QC coverage as requried (sic) for safety-related work by the QA/QC program.
"The completions punchlist . . . requires the assigned startup test engineer at approvimately 6 to 8 weeks prior to a target turnover date (or when assigneo) tc conduit (sic) periodic walkdowns and compile i punchlists cf uncompleted work, missing components and or damaged equip-ment. A test release (TR) is subsequently issued at time of system is turned over to TUGCO. The completions punchlist of incomplete items is attached. This punchlist is system oriented. Work on a system after TR requires a startup work authorization (SWA)..
"The tracking of component / system problems after turnover to startup tes cing -is termed the ' Master System Punchlist' . .. "
(Emphases added.)
T, . SPECIFIC PROBLEMS (continued): Thermal Expansion Test (CASE Exhibit 860) -- ICP-PT-55-ll During the discovery phase of the DP&L rate hearings, CASE requested a few documents (out of many) in regards to the test of thermal expansion (PTP-1-CP-PT-55-ll), item 20 of CASE's request (see CASE Exhibit 860 attached). Part of the information requested was the test procedure for the thermal expansion test and a artion of the acceptance criteria. As will be shown below, the Applicants appear not to have met the test objective. And although the acceptance criteria shown on the single page we requested for purposes of the rate hearings is not complete, the Applicants also appear not to have complied with the acceptance criteria. CASE also requested as part of the items relating only to the thermal expansion test (and did receive) 16 Test Deficiency Reports (TDR's) out of 420 TDi."s for the thermal expansion test. Based on these few TDR's, CASE offers the following summarization (which can be verified by reviewing CASE Exhibit 860 attaciled): 63 supports containing snubbers hac the snubbers removed or the support modified after the ther nal expansion test due to binding 23 cipe whip restraints were not installed during the test 179 snubbers were not installed on the pipe supports during the test 31 support locations exceeded the acceptance criteria by 10 per cent tie rods to the reactor coolant pumps had to be replaced due to ' binding (one TDR was used to change the effects of one support from a snubber to a rigid support -- of significance because it was one of the specific supports contained in CASE Exhibit 6698, Attachment to Jack Doyle's Deposition /Tes timony)
SPECIFIC PROBLEMS (continued): Thermal Expansion Test (CASE Exhibit 860) (continued): As stated on the second page of CASE Exhibit 860 (shown as page 3 of 152), the objective of this test was as follows:
" Portions of this test will be conducted in conjunction with PT-55-02
' Hot Functional' test procedure to verify that the ASME Code Class 1, 2 and 3 systems and other non-safety class systems which operate at a temperature greater than 2000F are not restrained during heatup to test temperatures or during cooldown to ambient conditions. This will in-clude verification that loads and clearance gaps of selected piping system snubbers, spring hangers & pipe rupture restrains (sic) are properly set for free pipe movement.
"In addition, this test will be utilized to obtain thermally related baseline data for preservice inspection and to determine the physical dimensions of required support and restraint shims."
The acceptance criteria for this test are as follows:
"2.1 Piping systems tested can expand and contract withou_t interferencc during heatup and subsequent coolda:r to ambient coPJitions.
"2.2 The 9,aps for supports and restraints which require shimming are sufficient to allow shim installations.
'2.3 The hot loads on the variable spring hangers are within the tolerances --~~
specified_ in Table I. .
"2.4 The travel indicators on the constant spring hangers are within the hot position tolerances specified in Table I.
"2.5 Snubber travel at the hot and return to ambient conditions are within the tolerances listed in Table I."
4 (It should be noted that CASE had requested Vol. I Tab I; as shown on the first page of CASE Exhibit 860, Applicants' response was that this Test Summary Report was not available: " Test procedure data package has not been finally ass.embled for review, therefore, Test Summary (Tab I) has not been prepared.") 4 I e 4 __ . . _ , _ . _ . . , , . - _ _ .m., , . - - , ...
SPECIFIC PROBLEMS (continued): Thermal Expansion Test (CASE Exhibit 860) (continued): A more detailed summary of the test results is shown below (which includes three supports from CASE Exhibit 6698, Attachment to Jack Doyle's Deposition / Tes timony) . This summery contains information r0gardirig the require retests as well. In general terms, it appears that Applicants would like to load fuel and then monitor the systems to see if_ they function correctly. TDR 1183 -- (CS) Chemical & Volume Control system -- 5/18/83 i Snubber found to be mechanically inoperative; removed for investigation and analysis. REQUIRED RETEST: " Snubber must be checked during heat-up to hot stand-by" TDR 1119 -- various systeas -- 4/29/83 11 (or 14?) snubbers remcved to perform modifications on supports or snubbers. REQUIRED RETEST: " Snubbers to be checked during heat tp to hot stand-by"
~
TDR 1112 -- various systems -- 4/29/83 14 snubbers removed because of bi'nding. REQUIRED RETEST: " Snubbers to be checked during heat-up to hot stand-by" TDR 1035 -- various systems -- 4/26/83 5 snubbers renoved due to exceeding travel capabilities (3 bottomed out, 2 topped out). REQUIRED RETEST: " Snubbers to be checked during heat-up to hot stand-by" TDR 1007 -- various systems -- 4/25/83 7 snubbers removed to perform modifications on supports er snubbers. , REQUIRED RETEST: " Snubber to be t>ecked during heat-up to hot stand-by" (Em;;hases added.) 1
SPECIFIC PROBLEMS (continued): Thermal Expansion Test (CASE Exhibit 860) (continued): TDR 1006 -- various systems -- 4/25/83 , 16 (or 17?) snubbers not installed pricr to Hot Functional Test (HFT). CORRECTIVE ACTION: " Snubber are to be installed after HFT per design. The omission of these snubbers has been reviewed and it has been deter-mined that their omission will not affect the HFT test results." REQUIRED RETEST: " Snubbers must be checked during heat-up to hot stand-by" TDR 971 -- Feactor Coolant system -- 4/15/83 Tie Rod #TR-3 on Reactor Coolant Pumps 1, 2 & 4 is binding on the side of the wall bracket and restricting normal pump movement. The tie rod TR-3 has been removed from all three pumps." REQUIRED RETEST: " Tie rod movements to be checked during heat-up after modifications are made" TDR 855 -- various systems -- 3/30/83-17 snubbers were removed due to binding in structural clevis or pipe attachment. (One of them was bent.) REQUIRED RETEST: " Snubbers must be monitored during heat-up to hot stand-by conditicr.." TDR 747 -- various systems -- 3/14/83
)
23 pipe whip restraints were not installed. 1 1 CURRECTIVE ACTION: " Install the PWR's after HFT to engineering design documents." , I REQUIRED RETEST: "PWR's will be monitored during power ascens *Sn" (Emphases added.) l
SPECIFIC PROBLEMS (continued): Thermal E::pansion Test (CASE Exhibit-860) (continued): TDR 744 -- various systems -- 3/15/83 5 snubbers removed because of binding in the rear or forward attachment bracket. " Hanger redesign or rework will be required." REQUIRED RETEST: " Snubbers to be checked during heat-up to hot stand-by" It should be noted that this TDR contains a reference to snubber MS 001-005-C72K. CASE Exhibit 669B, page 4R, listed support MS-1-001-005-S72R. It appears that this support was moved from the Safeguards Building to the Containment Building and changed from a Rigid support to a support with a S_nubber. TDR 722 -- various systems -- 3/7/83 162 snubbers were not installed. CORRECTIVE ACTION: " Snubbers are to be installed after HFT per design. The omission of these snubbers has been reviewed and it has been de-termined that their omission will not affect the HFT test results." REQUIRED RETEST: " Snubbers must be checked during heat-up to hot stand-by.i' It should be noted that on page 8 of 9 of this TDR, pipe support RH 008-008-S22K is indicated as not having snubbers. This is the support shown in CASE Exhibit 669B (Attachment to Doyle Deposition / Testimony), 1 ! page 13BB. Also, on page 2 of 9 of this TDR, pipe support MS-1-344-004-l C52K is listed; this suppa.-t is also shown in CASE Exhibit 669B on page 13CCC. Both supports were s%mped "As-Built" as shown in CASE Exhibit l 669B. In addition, the NRC SIT testified that it believes the design status of the pipe supports identified by Messrs. Walsh and Doyle fell I into steps (4) and (5) of the 9-step procedure outlined by the SIT on l l l l
$PECIFIC PROBLEMS _ (continued):
Thermal Expansion Test (CASE Exhibit 860) (continued): pages 14-16 of the SIT Report (NRC Staff Exhibit 207); in step 3, the sit stated that "When the pipe and some of its supports have been installed, the Quality Assurance Group starts its as-built inspection documenting the as-built dimensions of the pipe and installed pipe supports." If the Quality Assurance Group indeed had inspected these two supports.
- hrw is it that they were not even installed at the time o'f this Thermal Expansion test?
TDR 1477 -- Safety Injection system -- 7/1/83 Pipe at two support locations exceeded acceptance criteria, one by 20% Hot Position, and the other 20% Hot Position and 10% Final Ambient.
"(Gibbs & Hill scope)"
REQUIRED RETEST: None indicated. The box for " Engineering Evaluation of Deficiency Required" is marked "Yes." TDR 1490 -- Residual Heat Removal system -- 7/1/83 Pipe at 9 support locations exceeded acceptance criteria, 7 by 10% Final 1 Ambi at, and 2 by 20% Hot Position and 10% Final Ambient.
"(Gibbs & Hill scope)"
REQUIRED RETEST: None indicated. The box for " Engineering Evaluation
- of Deficiency Required" is marked "Yes."
TDR 1509 -- Main Steam system -- 7/1/83 Pipe at 4 support locations exceeded acceptance criteria, 3 by 10% Final
- Ambient, and 1 by 20% Hot Position and 10% Final Ambient. ! "(Gibbs & Hill scope)"
REQUIRED RETEST: None indicated. The box for " Engineering Evaluation l of Deficiency Required" is marked "Yes." l l (EmphasM added.) ! I
)
. o SPECIFIC PROBLEMS (continued):
Thermal Expansion Test (CASE Exhibit 860) (continued): TDR 1618 -- Component :ooling system -- !/1/83
+
Pipe at 16 support locations exceeded acceptance criteria, 6 by 10% Final Ambient, 6 by 20% Hot Position, .and 4 by 20% Hot Position and , 10% Final Ambient. . "(Gibbs & Hill scope)" RFQUIRED RETEST: None indicated. The box for " Engineering Evaluation of Deficiency Required" is marked "Yes." TDR 1666 -- Reactor Coolant system -- 7/25/83 1 Snubber to be changed to a rigid. CORRECTIVE ACTION: Install new support. REQUIRED RETEST: "Not required." (Emphases added.) As previously stated, CASE received just one page of the test procedure (for purposes of the DP&L rate hearings), and that page contained a partial listing of acceptance criteria. Item No. 2.5 of the criteria states:
" Snubber travel at the hot and return to ambient conditions are within the tolerances listed in Table I."
The test objective states, in part:". . . verification that loads and
". . . verification that loads and clearance gaps cf selected piping system snubbers, spring hangers & pipe rupture restrains (sic) are properly set for free pipe movement."
It is apparent that the Applicants have not met the test objective with 179 snubbers missing, 23 pipe whip restraints missing, and 63 supports contain- , ing snabbers having the snubbers removed or the support modified due to Dinding.
. . _ _ _ . - . ~ , _ . . _ . _ _ _ _ _ _ _ .
SPECIFIC PROBLEMS _ (continued): Thennal Expansion Test (CASE Exhibit 860) (continued): The Applicants noticed the snubbers were missing only when the acceptance criteria required them to see if the snubbers were within the required travel ra nge. There is no indication that the Applicants reinspected the supports for weld size, member size, configuration of support, proper preload of bol ts , e tc. As indicated on the one page of the test procedure, the Applicants did not monitor the systems in the Auxiliary Building, and did not indicate any missing snubbers in the Auxiliary Building. In addition, 31 supports are indicated to have exceeded their support locations. Many of the snubbers that were installed had mechanical problems such as binding, exceeding travel capabilities, or just being inoperative. The Applicants' position on this seems to be to remove the snubbers during the Thennal Expansion Test and reinstall them later. Thus , Applicants are not addressing the true problem, which is: Why did those supports malfunction to begin with? CASE believes that part of the answer to that question may be due to engineering (possibly by "somewhat knowledgeable" engineers??). Engineering may not have considered the support configuration; i.e., cinched-up U-bolts, unstable pipe supports, welded stanchions to the piping, impraper evaluation of support stiffness, to list just a few. Other answers may be due to con-struction. For example, were the supports built as shown on the as-built drawings; i.e. snubbers in place, welds to specified size, bolts proper torqued, correct member sizes, etc.?
SPECIFIC PROBLEMS (continued): Thermal Expansion Test (CASE Exhibit 860) (continued): The true significance of the problems the Applicants are having and the resolution of those prc;,lems has not been properly assessed. For example, with regard to the snubbers which must be monitored during heat-up to hot stand-by, the public has no assurance that those snubbers will be installed or can operate properly in the event of a seismic load during power ascension, much less that t'n ey will operate properly in the future.
. Applicants have performed the test in an improper manner to begin with since major components or items of equipment were not installed at the time of the test. Further, it is apparent that they have no intention of perform-ing additional tests following installation of some components or equipment to assure they will operate correctly. Clearly this is improper, immoral, and contrary to NRC regulations, specifically 10 CFR Part 50, Appendix B, Criterion I, which states in part:
"The quality assurance functions are those of (a) assuring that an appro-priate quality assurance program is established and effectively executed and (b) verifying, such as by checking, auditing, and inspection, that activities affecting the safety-related functions have been correctly performed."
. . . and 10 CFR Part 50, Appendix B, Criterion XI. TEST CONTROL, which states:
"A test program shall be established ta assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test prewires which incorpor_te the requirements and acceptance limits contained in applicable design documents. The test program shall include, as appropriate, proof tests prior to installa-tion, preoperational tests, and operational tests during nuclear power plant . . . operation, of structures, systems, and components. Test procedures shall include provisions for assuring that all prerequisites for the given test have been met, that adequate test instrumentation is available and used, and that the test is performed under suitable environmental conditions. Test results shall be documented and eval-uated to assure that test requirements have been satisfied." (Emphases added.)
SPECIFIC PROBLEMS (continued): Containment Temperature Survey (CASE Exhibit 857) -- 1CP-PT-45-06 Engineering evaluation was required prior to retesting section 7.1 containment temperature survey, which was tested a total of 3 times. Upon completion on 3/27/83 it was discovered that the temperature indicators were unreliable in ambient temperature above 1040 Test Deficiency 839 was issued and section 7.1 was required to be retested. Retest for TDR-839 completed on 4/5/83 and TDR-908 issued to identify areas that do not meet acceptance criteria. Upon completion of engineering evaluation the Containment Ventilation System was adjusted. Due to Hot Functional Testing the changes in pressurizer area could not be initiated. Section 7.1 was retested on 5/18/83 and the same areas addressed in TDR-908 still did not meet this acceptance criteria. TDR-908 was closed and TDR-1221 issued against section 7.1. There were a total of 15 Test Procedure Deviations and 5 Test Deficiencies issued during the conduct of this test. The follcwing test deficiencies remain open at the conclusion of this test. (Report is dated 6/1/83)
- 1. Test deficiency report 1043 issued again section 7.10. This section cannot be tested until initial startup, because normal operating temperature was not reached during Hot Functional Testing for this area.
- 2. Test deficiency report #1221 issued against Section 7.1 Containment Survey. Various areas in section 7.1 did not meet their respective acceptance criteria. This area will be tested during initial startup.
As stated in TDR 908:
"The following areas did not meet the acceptance criteria:
"1. R.P.V. (Reactor Pressure Vessel) supports #1 Hot Leg, #2 Cold Leg, #3 Hot Leg, #4 Cold.
"2. Detector wells" (3)
"3. PZR Room 905 "4. Steam Generator Compartments #1,. #2, #3, #4.
I "See CPPA-29.488 ' Minutes of Meeting' on April 20-21, 1983 (attached) for corrective actionr. K. F. Mcdonald 5/3/83" (NOTE: The Minutes of the April 20-21 meeting were not attached to CASE's copy of TDR 908 r:5en we received it from Applicants.)
" Engineering Evaluation of Deficiency Required: Yes."
y e - - - - v -e - , - - - - - -y # -%y , ---- - n-- -- -
f
; SPECIFIC PROBLEMS (continued):
. Containment Temperature Survey (CASE Exhibit 857) (continued): 3 In addition to the problems experienced regarding the Containment Atmos-('., phere, there were also problems experienced with the Main Steam and Feedwater Penetration Area Cooling System (see TDR 1043): A
., "Section 7.10 cannot be completed during HFT because feedwater system
, i normal operating temp. will not be reached.
d " CORRECTIVE ACTION: This area to be tested during initial start-up." (Emphasis added.) The System Test Engineer recommends approval of the test as performed. The objective of this test is stated to be "to demonstrate the ability of the following ventilation systems to maintain their respective areas at or below the maximum allowable design temperature:
" Containment Recirculation Cooling System .
a_ " Neutron Detector Well Cooling System
- y " Reactor Coolant Pipe Penetration Cooling System
" Main Steam and Feedwater Penetration Areas Cooling System
" Control Rod Drive Mechanism Ventilation System "R.H.R. (Residual Heat Removal) Pump Rooms Cooling Systems 4 " Centrifugal Charging Pump Rooms Cooling Systems
" Component Cooling Water Pump Rooms Cooling Systems
" Positive Displacement Pump Room Cooling System
" Auxiliary Feedwater Pump Rooms Cocling Systems -
"Safetv Injection Pump Rooms Cooling Systems
" Containment Spray Pump Rooms Cooling Systems "The containment temperature test will be perfonned during the Hot Functional Test Sequence while the other areas will be tested by simulating the maximum design heat load the areas are designed for."
Obviously, Applicants did not meet the design criteria or achieve the test objective. Further, they apparently have no plans to perform any retests prior to initial startup.
R SPECIFIC PROBLEMS (continued): Control Room Heating & Ventilation System Performance (CASE Exhibit 859) - XCP-PT-0 7-01 "The status of Control Room HVAC System at the end of the preoperational test .is as follows:
" System functions per design. Temporary modifications 124-127 were left installed because smoke detectors are not functional. Temporary modifi-cations 130-133 were left installed because radiation monitors are not functional, chlorine detectors were left in the 0FF position because they had not been calibrated, as of this date.
"The System Test Engir.eer recommends approval of the test as performed."
Dated 6/9/83. (Emphases added.) a i f
,,----,.-,.-.~r -. .. -.. _ ~ ~ _ - _ - - - - ---+,-m ,v. , --. - . . . . - - - , _ - ,,,, , ,
_ ~ SPECIFIC PROBLEMS (contin 9ed): Steam Generator Safety and Relief Valves (CASE Exhibit 862)(lCP-PT-34-02) The test objective was stated to be: ,
"This test will demonstrate the proper functioning of the steam generator safety and . power-operated relief valves."
TDR 947 -- During testing, steam filled the valve room when the Relief Valve opened more than 50% and burned the STE and other testing personnel con-ducting the test. That valve (1-PV-2327) was the third Relief Valve tested, but it was tile first to have steam exhaust into the valve room. The following day, two other Relief valves were opened and steam again exhausted into the valve room. Several days later the same valves were opened again and the exhaust stacks provided complete exhaust, except for a small amount of steam which came out the drain piping when the valves were between 90 to 100% open. The exhausting problem seem:; to be dependent on the wind strength and speed, which could cause back pressure at the top of the exhausting pipe and push some of the steam back into the room. Steam emptying into the room presented direct hazardous conditions to personnel and for extended valve opening, possible equipment damage. CORRECTIVE ACTION: Redesign exhausting piping. Engineering evalua-tion required. Required retest: Steps 7.1.58 and 7.1.59 of ICP T-34-02. CMC's issued. The modification of TDR 947 remains to be implemented (no testing of the exhaust piping modification is required). TDR's 1039,1040,1041,1042,1049,1050,1051 -- Valves failed to pass set point test. Reset and repeat steps. TDR's 1053,1054,1055,1C'id,1057 -- Valves, when tested the second time, tested between 17-26 psig below the as left set-point from the original test. TDR 961 -- During testing of accumulators, accumulator pressure fell below required amount to maintain full valve position; actiator diaphragm has a small leak, which allows air pressure to vary from acceptable. Iaspect and repair / replace as necessary. Retest Section 7.7. Diaphragm is currently on order. Retest for TDR 961 will he performed after replace-ment of the diaphragm. TDR 1192 -- Valve lifted at 14.8% above the set point pressure; loop should be recalibrated. Retest for TDR 1192 will be performed after HFT. Recalibration and retest remain to be performed. TDR 1169 -- concerns the validity of the test results, due to the fact that 15 valves were left unattended before the seals were placed on the valves. Corrective action was to reverify the set points of the un-attended valves by retesting each valve. This was conducted and TDR was closed. All the tests on pages 3 through 22 of TDR #1169 were shown to have been done on 4/28/83. CASE questions whether this was possible.
SPECIFIC PROBLEMS (continued): Containment Integrated Leak Rate Test (CASE Exhibic 863) - ICP-PT-75-02 The reduced pressure test was successfully completed on the first cttempt, however, the peak pressure test was not successfully completed until the third attempt. The three attempts at the peak pressure test were a result of numerous leaks that were encountered in the steam generators and associated piping and instruments. A total of 24 test procedure deviations were written, of which two re-quired JTG approval. There were six test deficiencies identified; no open items at end of testing. TDR 562 and 574 -- Resulted from measured leakage rates greater than acceptance criteria during 1st and 2nd attempts at peak pressure test. Containment was depressurized and entries made to correct leaks and valve
- lineups associated with the steam generators and connecting piping. After .
making corrections, a third peak pressure test was successfully performed. TDR 587, 566, and 565 -- Resulted from leakage through electrical pene-trations. Each penetration was isolated during peak pressure test to re-duce overall peak pressure test leakage. One penetration leakage mechanism was readily identified and successfully corrected. However, penetra-tions E-68 and E-49 exhibited uni-directional leakaga and required per-formance of a special test to identify the leakage mechanism and sub-stantiate the repair as sctisfactory. The 3 penetrations were all successfully repaired and loc?1 leak rate tested. TDR 567 -- Issued as a result of leakage through personnel airlock interior and differential pressure switch vent valve. The valve was replaced with valve from Unit #2 personnel airlock prior to third peak pressure test. l
~ , , p --,
e - .- - - - - -
r e SPECIFIC PROBLEMS (continued): Reactor Coolant Pump Test (CASE Exhibit 861) - 1CP-PT-55-09 CASE had requested Tab I and Tab VII as part of the documents regarding this test. Applicants' answer was (CASE Exhibit 861, page 1):
" Test procedure data package has not been finally assembled for review, therefore, Test Summary (Tab I) and Outstanding Items (Tab VII) have not been prepared."
TDR 1089 -- Certain test requirements were not satisfied in that a chrono-logical test log was not maintained, equivalent problems resulting in TDR's were not logged and correcticns/ additions to data sheets 13,14, 15 and 16 were made without processing a TPD in accordance with procedure. CORRECTIVE' ACTION: " Process necessary TPD's and construct a chrono-logical log to document the testing activities and deficiencies which occurred during conduct of Section 7.2.2. Counsel the STE's on compliance
' wi th CP-SAP-21. "
REQUIRED RETEST: "None." TDR 111.4 -- Reactor Coolant Pump Seals did not meet acceptance criteria. CORRECTIVE ACTION: " Repair / replace / inspect reactor coolant pump seals as necessary." REQUIRED RETEST: " Establish conditions as necessary and reperform step 7.2.2 of ICP-PT-59-09Rl ."
" Engineering Evaluation of Deficiency Required: No."
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r SPECIFIC PROBLEMS (continued): Auxiliary Feedwater Turbine Driven Pump (CASE Exhibit 856), ICP-FT-37-03 During the conduct of this preoperational test, problems found included the following (as well as other problems): Turbine-Priven pump was unable to produce rated flow or pressure when steam pressure wA3 lowered to 110 psig <(TDR 1142). Resolution was to accept as is. Turbine Steam supply valves leak, preventing the cool down of steam supply piping for cold starts. TPD #13 was written to cool down the steam' piping by securing the manual isolation valves just up stream of the leaking valves. Resolution of TDR 1084 is to rework the valve settings. Rework remains an open item to this test. The Turbine speed control loop did not control properly (TDR 1001). After many attempts to recalibrate it was determined that it was not possible as designed (TDR 1199). TDR 1199 remains open awaiting TUSI Engineering Evaluation. TDR 902 -- Flow control valve controller did not function properly. TDR 1086 -- Pump discharge indicator failed to function properly. TDR 1087 -- Turbine speed indicator at hot shutdown panel failed to function properly. " Repair or recal . as need. Loop cal (no preop retest required)." TnR 1118 -- Turbine driven Auxiliary feedwater pump did not operate at minimum steam generator pressure of 125 psig or 110 psig. TDR 1083 -- Level switch stuck closed and therefore drain pot drain valve failed to shut after condensate was drained from steam piping. Replace level switch with one that will work at high temperature; engineering evaluation requested. TDR 1157 -- motor driven punp tripped on low suction during water ham er test. TDCR previously submitted to insert a 5 second time delay to defeat low suction pressure during starting. TDCR not yet approved but will correct the problem. Corrective action - write a TPD to allow holding the start switch in start momentarily in step to complete water hammer test. REQUIRED RETEST: Do Step 7.9 with TPD 21. TDR 1016 -- outboard pump bearing exceeded allowable temperature of TB00F. Add pump bearing cooling line; rework completed; required re-test section 7.10 (48 hour run).
- . - - . _ _m., - _ ._-
SPECIFIC PROBLEMS (continued): Auxiliary Feedwater Turbine Driven Pump (CASE Exhibit 856) (continued): TDR 1017 -- Temperature of Steam Generator Room #74 exceeded allowable temperature of 1040F. Trit was run with . supply and exhaust dampers open with ventilation system in operation. CORREC7IVE ACTION: Use as is. See 5/19/83 letter from Gibbs & Hill, following TDR 1279. TDR 1279 -- Relative humidity of Steam Generator Room #74 (same as in above TDR 1017) exceeded allowable of 70%; was un to 95% then back to 70%. Use as is. See TDR 1279. TDR 1085 -- During shut down of turbine, trip and throttle valve failed to shut when the trip solenoid was energized and the trip leve released; this condition is only found when valve is het and steam pressure is greater than about 500 psig. Rework / clean valve parts and retest. i
~
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SPECIFIC PROBLEMS (continued): Hot Functional Test Sequence (CASE Exhibit 858) - ICP-PT-55-02 See discussion on pages 23 and 24 of this pleading regarding other tests which are incorporated into the Hot Functional Test Sequence (see also fifth and sixth pages of CASE Exhibit 858). For details of various tests which were performed during Hot Functional Test (HFT), see che test sunmary for that particular test. TDR 679 -- After filling and pressurizing the Reactor Coolant System (RCS), the primary side drain valve on steam generator #4 developed a body-to-bonnet leak which required depressurization and draining of the RCS. Repair of the valve required a two day delay in the schedule. Concerning Thermal Expansion Test (see pages 25-34 of this pleading), as the various testing plateaus were reached (250F, 350F, and 450F), the thermal expansion program of PT-55-ll required significant time to measure, evaluate, and re-measure the large number of pipe supports involved in the program (over 4000 supports were involved). The _ instrument calibration program, as expected, caused long delays in heating up the plant. This delay was expected since many instrumentation loop calibration procedures were not available prior to HFT. Therefore plant evolutions were held up until the required instruments were cali-brated. At the 450F plateau it was determined that RCP #3 tie rod TR-3 was binding in its wall bracket and the tie rod was required to be removed (see TDR-846). This necessitated plant cooldown to 325F to free the tie rod for removal and subsequent heatup to restore plant conditions. Approximately two days were devoted to this evolution. The testing ' generally proceeded in an expeditious manner, although there were several delays for equipment repairs, retests, or procedure prepara-tion. There were 90 cooldowns during the hot standby phase. The first, on April 13, was required in order to free the tie rods, causing a three-day delay (see TDR-971). The second cooldown, which lasted from May 2 to. May 8, was required in order to mc%e several repairs. The letdown orifices which failed their acceptance criteria during PT-49-02 (by providing too much flow) were re-placed during this period. Charging valves which had developed body-to-bonnet leaks, were scheduled for repair, but since upstream check valves leaked through, only the bonnets were torqued and the valves will be repaired after HFT. Also, during the cooldown,1-8141D (RCP #4 seal return isolation) was repaired due to binding of valve internals.
SPECIFIC PROBLEMS (continued): Hot Functional Test Sequence (CASE Exhibit 858) (continued): At the end of the hot standby phase there were additional delays due to BTRS chiller problems which prevented speedy completion of the RCS boration and dilution tests of PT-49-05. TDR 945 -- (to PT-49-02) - Chemical & Volume Control - RCP -- High flow rates from all #2 seal leakoffs for Pumps #1, 2, 3, and 4 -- T9R is open. TDR 894 -- (to PT-55-02) - RCP #3 No. I seal leakoff flow too great. TDR is closed. TDR 691 -- Thermal trip did not occur in required time range; inst'antaneous adjustable trip did not occur in correct amp range. TDR 954 -- RCP #4 tripped after R;P #2 was started. TDR 955 -- RCP #2 Breaker tripped after closing. TDR 1114 -- (to PT-55-09) seal flow problems on all RCP's No.1 and No. 2 seal leakoff flagrates and RCP #1 and #2 No. 3 seal flowrates. TDR is open. TCR 1200 -- RCP #3 No. 3 seal leakage to atmosphere. TDR is open, corrective action to be performed on TDR-lll4 preceding. TDR 1270 -- Auxiliary Feedwater system - during control of plant from remote shutdown panel, instrumentation problems occurred (as faulty readings were noted). Functional check each item to assure proper indication. TDR 1276 -- Steam Generator chemistry started out in poor shape, as was expected for the first heatup of the carbon steel secondary-side. How3ver, the steam generators were gradually cleaned up using the blow-down and condensate polishing systems and at the end of HFT the steam generator chemistry was fairly consistent. No corrective action required. TDR is closed. TDR 1277 -- Reactor coolant and pressurizer were out of specification on silica concentrations during HFT from 3/6/83 to 3/14/83. Lithium concentration periodically dipped below limits. No corrective action required. CVCS demineralizer was employed to reduce silica concentra-tion. Lithium hydroxide was added as necessary to return the lithium concentration to specification. No required retest. P
- - . r -, - - -
f SPECIFIC PROBLEMS (continued): Hot Functional Test Sequence (CASE Exhibit 858) (continued): TDR 1323 -- Reactor coolant-system to steam generator secondary differential pressure was exceed because of procedural violations by system test engineers. CORRECTIVE ACTION: 1) Counsel affected System Test Engineers who violated the procedure. 2) Update chronological test log to include the reconstructed. events and graph. 3) Have Engineering evaluate the , effect of exceeding the 1600 psic limitations. TDR 1909 -- Chronological log for PT-55-02 (Hot Functional Test Sequence) did not fully comply with SAP-21 paragraph 4.10.7. in that some "Significant , Events" and some " Problem Resolutions" were not logged (Examples: TPD's written, Steps performed, and Test Deficiencies corrected). In addition, extraneous information irrelevant to test performance was entered in the log. CORRECTIVE ACTION: Research the procedures performed during HFT and assemble the pertinent information required by SAP-21 into a new
-l og. Enter this new log into the procedure.
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c l SPECIFIC PROBLEMS (continued): MAJOR PROBLEM AREAS As discussed on pages 15 and 16 of this pleading, the number of documents regarding Hot Functional Tests and other tests done befori fuel load is over-whelming, and CASE has attempted to keep the number of documents attached hereto down to a manageable number, while at the same time retaining enough documentation to give the Board a feel for the types of problems involved and to point out some of tha problem areas which appear to be most significant. In addition to the items discussed in the preceding, CASE has attached portions of the two punchlists which we received on discovery in the DP&L rate hearings: The full listing of the Main Steam System from the Master System Punchlist, 5/25/83, Subsystem No. 3401, pages 955-1,089, and from the Master Data System punchlist, 9/23/83, Subsystem No. 3401, pages 249-282 (CASE Exhibits 864 and 865, respectively; see discussion on pages 15 and 16, items (3) and (4), of this pleading); and selected pages from the 9/23/83 Master Data System punchlist (CASE Exhibits 866 through 874). These pages should be sufficient to give the Board an idea of some of the types of problems I identified on the punchlists; and we point out specific items from them below. Inchded in the ' problems identified on the punchlists are the following; j from the Master Data System punchlist, 9/23/83; CASE Exhibit 865: Main Steam System, Subsystem No. 3401: Item No. 00015 - 2" plug improperly removed in Steam Generator #2 and permanently plugged. Permanent plug now determined to be not permanent, , needs replacement. Plug installed but rejected by Westinghouse. Work l to be completed under MAR-82-0249. Need leak test. Work completed 10/19/82. Steam Generator #2 requires re-hydro. to be performed prior to fuel load. ESD-9/30/83.
SPECIFIC PROBLEMS (continued): MAJOR PROBLEM AREAS (continued): Main Steam System (continued): Item No. 0020S - Temporary support installed to provide proper deadweight support for testing; permanent support to be installed after HFT; TUR 0721; 55-11. Item 0143S - Changes to 8 Steam General blowdown isolation valves. 44-03. Item 0051S - Main steam loop 2 drain pot level switch has defective microswitch. Generic problem. IE needs to design micro switch; protection parts are on site; work is in progress. TDR 0993. 34-04. Items 0C03S through 0102S - During work on main steam stop valve actuators, it was found that the hydraulic oil is contaminated. Condition cf internal seal and pump is indeterminate. Qualified actuator to be .in-stalled before fuel load. Instr. & Elect. need to complete their part. Item 0106S - Main steam heat is decomposing the components of the magnetial level switch. Ref: Item 0051S. FR for new switches. Matl. shipped 8/12/83. Installation of micro switches in progress. IE to have level switch heat fins designed. TDR 1144. 34-04. Item 0143S - Changes to Steam Generator Blowdown isolation valves (8). 44-03. Items 0234S through 0289S - pipe at support locations exceeds acceptance criteria. Various TDR's. 55-11. Gives an idea of magnitude of this particular type of problem in Themal Expansion test. (See pages 26 through 34 of this pleading.) See also items 0327S-0340S; most "0K.as is." Items 0290S through 03095 - supports exceed acceptance criteria. Various TDR's. 55-11, Thermal Expansion test. In some cases, no disposition is given; in others, it is stated " Engr. complete; accept. criteria was changed"; in others, it is stated "no engr. required; this is not a problem"; e tc. Item 0477S - Parts of the spools are in a section of main steam piping that has been cut out for modifications. Pipe ends have been left open allowing debris to collect in line. System cleanliness is lost. Extensive grind-ing on open end of valve has allowed grinding sparks and debris to collect inside valve body. Some adherions to internals occurred. Dispo: Repair. NCR. (Emphasis added.) See also discussion with Mr. Spence, President
- of TUGC0, at Tr.150-154 (especially 153), in 10/3/83 DP&L rate hearings, copy attached. (See also Board Notification 83-11, and discussion by NRC Staff counsel in the 3/18/83 letter to the Board regarding the Staff's evaluation of Board Notifications filed in this proceeding.)
. SPECIFIC PROBLEMS (continued):
MAJOR PROBLEM AREAS (continued): Reactor Coolant System, Subsystem No. 5$01 (CASE Exhibit 868): Item 0001S "W" Pressurizer required documentation incomplete. Need completed stress report; awaiting quality release. Not dispo'd. per QC. NCR. Item 0009S - West.' Steam Generators #1 and 2 have eddy current indications greater than 40% in some tubes which requires that the tubes be plugged. Awaiting quality release. QR will dispo NCR. Item 0010S - (W); Eddy current testing revealed a # of tubes in each Steam Generator which need to be rolled. TUGC0 NCR written against tubes naeding rolling. Awaiting quality release. QR will dispo NCR. Reactor Cooiant System, Subsystem No. 5501 (CASE Exhibit 869): Items 0132S through 0134S - Repair and modify Steam Generator Snubbers, Loops 1, 2, and 3. Snabbers to be replaced. Polar Crane, Subsystem No. 8104 (CASE Exhibit 870):
. Item 0001C - All changeover equipment to 175 ton plant lift configuration for the polar crane.
Item 0019S - Declassification of the polar crane from 425 tons to 175 tons for seismic qualification. Kranco Service Manual. Item 0031S - Vendor drawings need to be revised to reflect as-built conditions. Authorize use of Unit 2 drawings. Containment Fel Storage Crane, Subsystem No. 8109 (CASE Exhibit 871): Item 0001C - Install Cont. Fuel Storage Crane. Need Polar Crane to work. Containment Spray Chemical Addition, Subsystem No. 4802 (CASE Exhibit 872): Items 0019S, 00245, 0025S - Borg-Warner check valve was supplied with studs, nuts, and clappers secured by tack welding. This design is inadequate. NCR. Dispo: Rework. Need Closure. Items 00205, 0021S, 0023S - Borg-Warner check valve has an unacceptable amount of rust. Dispo. Rework. TUGC0 lapping. Waiting on hand lapping plate. NCR's. Items 0031S, 0038S - other problems with Borg-Warner valves. NCR. Dispo: Rework. i
. SPECIFIC PROBLEMS (continued):
MAJOR PROBLEM AREAS (continued): Items 0039S through 0041S - seal water heat exchangers and bearing cooling coils have been furnished without N-stamp and N-1 data report. The pump and the heat exchangers including bearing cooler coils have been installed. NCR 's . Dispo: 0039S, Seal water heat exchangers are to be returned to vendor; in addition, for 0040S and 0041S, SWA for removal only. Need FR. Need date for re-installation. Item 0098S - seal water and bearing coolers need to be returned to vendor for N-stamp and documentation. NCR. Reactor- Coolant System, Subsystem No. 5501 (CASE Exhibit 873): Item 0053S - Pressurizer P0PV leaking past seat. Need traveler when parts are received. TDR. Item 0163S - Westinghouse supplied PC#501, arc strike found on cross-member (PC#501) between Steam Generator #2 main support and Reactor Coolant Pump #2 main support. Condition is indeterminate. Dispo. RPS issued 4/07. NCR. Residual Heat Removal System, Subsystem No. 5801 (CASE Exhibit 274): Item 0031S - RHR Pump. TUGC0 was disassembling RHR motor-01. The rigging gave way causing indeteminate damage to motor and pump casing.
'NCR. Need R-1 dispo.
Item 0175S - While TUGC0 was disassembling RHR Motor 01, the rigging hold-ing the motor dropped back into the casing approx. 6" causing-indeterminate damage to motor and pump casing. Dispo: Repair. (same as item 0031S preceding??) Items 0042S and 00435 - temporary struts attached to RHR pumps 01 and S2 motors. Westinghouse conducting seismic analysis on perm. struts. Temp. unds. are cleared. Items 0105S through 01085 - RHR pumps had vibration readings exceeding allowable maximums. TDR's. b3-01, 57-06. Waiting for Westinghouse info. input on acceptable use of sway strut installation. Struts are temp. Will require DCA. West. to supply FCN if struts are to be made permanent. Steam Generator Chemical Injection & Recirculation System, Subsystem No.
- 3303 (CASE Exhibits 866 and 867)
Item 0026C - Steam Generator Recirc. System-Installation incomplete. Items 0051S and 0052S - Hydro's not complete. Pending system availability.
d j SPECIFIC PROBLEMS (c'ontinued): Major Problem Areas (continued): Because of the huge amount of documents represented by the very small
' sample ~ CASE received on discovery in the DP&L rate hearings (which were for a different purpose), it has been difficult in the short amount of time we have had the. documents to review, analyze, and prepare them in an orderly fashion as. ordered by the Board. It may well be that we could have done a little better job with more time. However, we believe tnat there are significant or potentially significant matters which are raised by the documents we hcve included. For this reason, we wanted to get them into the hands of tne Board as soon as possible. Additionally, we wanted '
to get them into the hands of the other parties as soon as possible, since there are some which we will be asking questions on in the upcoming hearings which begin October 17 (although we do not expect that our cross-examination on Ulen will be very lengthy since we have not had time to adequately prepare cross-examination questions). NEED FOR DISCOVERY Because of the nature of the information we were seeking in the DP&L 2 rate hearings, there are many questions raised by the information we have already received -- questions for which we can obtain no answer outside these cr.erating. license proceedings. Further, once we determine the functions of 4 the different punchlists and they way in which they are used, we need a current punchlist which will assist.the Board most advantageously. We need to have
. discovery in order to save the time of the Board and all parties.
s i
i INFORMATION OBTAINED IS RELEVANT, MATERIAL, AND VITALLY IMPORTANT FOR THE RECORD The importance of the results of the Hot Functional Test and other tests in preparation for fuel loading is obvious. This importance was emphasized by NRL Staff witness Robert Taylor, the NRC Resident Inspector - Construction at Comanche Peak, in his testimony in the June 10, 1982, hearings (see Tr. 1732-1737). He stated, in part: (JUDGEMILLER) "Q: . . . What I'm attempting to find out is your professional evaluation of the likelihood, as well as the existence, of any kinds of deficiencies that are not ridiculously insignificant.
. . . I just want your honest evaluation.
(WITNESS TAYLOR) "A. I have to assume that there are some. I'm not an unrealistic idiot. There are some deficiencies. I would hope they are not of very great consequence that have been remaining in the facility. The bulk of them will, I think, be weeded out in an ongoing testing pro-gram that leads up to the core loading, so to speak. These tests have been deliberately and I think carefully designed to detect those things, which if they malfunction would threaten the safety of the public.
"Most of this testing has not yet been done. .I allude specifically to the containment structural integrity, followed by the containment test.
"That test has not been performed. We don't know whether that contain-ment is going to perform the things that it is supposed to do. Now we're going to find out. We have attempted for several years -- we're still attempting now -- to build it. We hope it was designed properly. They are still closing up the so-called construction opening as of two weeks ago. That part of the construction phase is concrete, reinforcing steel, Cadwelds, labor hands, and whatnot doing the work. Put the final proof of the pudding is that test as well as a myriad of of.har tests that are run and (sic - believe this should be "on") a myriad of other systems."
/_6/ (Emphases added.)
6 It should be noted that Mr. Taylor went on to state (Tr.1735) that, although these tests had not yet been performed: "I would be very comfortable building a house on top of that plant and living in it for the entire future of my life and not be concerned whatever with my safety or my family's safety." 4
4 d
-S2-INFORMATION IS RELEVANT, MATERIAL, VITALLY IMPORTANT (continued):
Mr. Taylor also stated, in response to questions by William S. Jordar., III, CASE's attorney for the June 1982 hearings only (Tr. 1736-1737)':
"BY MR. J0RDAN: Q: Mr. Taylor, is it not the case that the quality assurance function as distinct from the program is in effect the last line of defen;e of the overall quality assurance program?
(BY WITNESS TAYLOR) "A. Final verification of part of the program, if you will, and it is a verification, hopefully, that the first part of the program worked properly.
"Q: So that if the first part of the program did not work properly, the quality assurance. function is where you find that out, correct?
"A: The last part of the quality assurance function. Remember, there are two functions.
"Q: Yes, indeed. . . ..I'll read it. This is Appendix B, 10 CFR Part 50, criterion one. Not reading the whole thing. Reading this sentence.
"'The quality assurance functions are those of (a), assuring that an appropraite quality assurance program is established and effectively executied, and, (b), verifying such by checking, auditing, and inspection that activities affecting the safety-related functions have been correctly performed. '
"That (b), Mr. Taylce, is in effect the last line of defense, correct?
"A: It is all encompassing and includes the testing program, the whole gamut of inspection, testing, verifying, whatnot.
"Q: And given that definition, the answer is yes, right?
"A: Give me the question again.
"Q: Whether that's the last line of defense.
"A: Yes."
(Emphases added.)
O e . CASE'S MOTION WILL NOT DELAY THE PROCFEDINGS CASE believes that the NRC Caseload Forecast Panel's report, which is
-due out at any time, will confirm that Applicants cannot possibly meet their allegad December fuel load date, and that it will be at least March 1984 before they can possibly be ready to load fuel. Further, from the documents attached hereto, CASE submits that a June 1984 (.if then) fuel load date is much more likely. The extent of the probleas still to be dealt with is awesome indeed and cannot be accomplished overnight if they are to be dealt with in a manner which assures that the public health and safety can be protected.
CASE'S MOTIONS For the reasons discussed herein, CASE hereby moves that the Licensing Board: (1) Grant CASE's Motien to Add a New Contention (or in the alternative, that all elements of our Proposed New Contention be litigated under the present QA/QC Contention 5); (2) Accept CASE's pleading and Offer of Proof in lieu of an answer to Applicants' inevitable Motion for Summary Disposition should our new Contention be accepted; (3) Grant CASE discovery on all matters relevant to our Proposed Contention;
4 c .. . (4) Recognize that Applicants are not responsive to the Boara's adnonish-ments to keep it informed of significant or potentially significant matters, au demonstrated by Applicants' blatant and deliberate attempts to withhold from the Board potentially significant in-formation and their attempts to keep CASE from advising the Board of this information; and (5) Grant CASE ninety days discovery regarding this Proposed New Contention, not only because it is warranted in order to adequately review and analyze the necessary documents and develop a complete and sound record, but also to convince the Applicants that the Board will not tolerate such willful withholding of potentially significant infc rmation. Respectfully submitted, t
/ L 5 fA *)
W s.) Juaniti Ellis, President TASE (Citizens Association for Sound Energy) 1426 S. Polk Dallas, Texas 75224 214/946-9446 l
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING ~ BOARD
.In the Matter of ! APPLICATION OF TEXAS UTILITIES ' } GENEF.ATING COMPANY, ET AL. FOR l Docket Nos.'50-445 -
AN OPERATING LICENSE FOR and 50-446
. COMANCHE PEAK STEAM ELECTRIC. (
STATION UNITS #1 AND #2 (CPSES) l CERTIFICATE OF SERVICE By my signature below, I hereby certify that true and correct copies of
~
CASE'S (1) MOTION TO ADD A NEW CONTENTION (CONTENTION 26), (2). MOTION F'OR DISCOVERY,AND(3)?0FFEROFPROOF have been sent to'the naus~ listed below this _13th day of. October , 1933 , by: ' Express Mail where indicated by
- and First Class Mail elset.nere. _
- Administrative Judge Peter B. Bloch Alan S. Rosenthal, Esq. , Chaiman ,
U. S. Nuclear Regulatory Comission Atomic Safety. and Licensing Appeal Board
- 4350 East / West Highway, 4th Floor U. S. Nuclear Regulatory Comission Bethesda, Maryl.and 20014 Washington, D. C. 20555
.
- Dr. Kenneth A. McCollom, Dean Dr. W. Reed Johnson, ' Member #
Division of Engineering, Atomic Safety and Licensing Appeal Board l Architecture and. Technology U. S. Nuclear Regulatory Commission Oklahoma State University Washington, D. C. 20555
. Stillwater, Oklahoma 74074 Thomas S. Moore , Esq. , Member
,* Dr. Walter H. Jordan Atomic Safety and Licensing Appeal Board 881 W. Outer Drive U. S. Nuclear Regulatory Comission Oak Ridge, Tennessee 37830 Washington, D. C. 20555 ,
- Nicholas S. Reynolds, 'Esq. Atomic Safety and Licensing Appeal Panel Debevoise & Libermari U. S. Nuclear Regulatory Comission 1200 - 17th St., N. W. Washington, D. C. 20555 Washington, D. C. 20036
. Docketing and Service Section (3 copies) l Marjorie Ulman Rothschild, Esq. Office of the ' Secretary Office of Executive Legal Director, USNRC U. S. Nuclear Regulatory Comission
! Maryland National Bank Building Washington, D. C. 20555 l 7735 Old Georgetown R0ad - Room 10105 Bethesda, Maryland 20Q 4 Atomic Safety.and Licensing Board ~ 0 Panel ? U. S. Nuclear Regulatory Commission Washington, D. C. -20555 1 9
. . - . , . .-......--v,,e __ - _ ,- _ . .-, ,_ ,%-m-e, -_,,-y . -..,__.,_ - , -,.. , - -
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Cert;ficate cf Service Page 2
- David J. Preister, Esq.
Assistant Attorney General Envirorsnental Protection Division'
- Supreme Court Building.
Austin, Texas 78711 John Collins Regional Administrator, Region-IV U. S. Nuclear Regulatory Comissici. ' 611 Ryan Plaza Dr., Suite 1000 . A:lington, Texas 76011 Dr. Oavid H. Boltz 2012 S. Polk Dallas, Texas 75224 Lanny A. Sinkin , 114 W. 7th, Suite 220 Austin, Texas 78701 O DJa Sfrs.) Juanita EllTs, President CASE (Citizens Association for Sound Energy) 1426 S. Polk Dallas, Texas 75224 214/946-9446 e G ,
?
'~ ' DOCKET NO. 5256 APPLICATI09 0F DALLAS POWER PUBLIC UTILITY COMMISSION AND LIGHT COMPANY FOR AUTHORITY TO CHANGE RATES l OF TEXAS EXAMINER'S ORDER RULING ON DP&L*S OBJECTIONS TO CA$E'S RFI'S On August 18, 1983, a prehearing conference was held to discuss Dallas Power and Light Company's (DP&L) objections to Requests for Information (;RFI) propounded by Citizens AssociationfcrSoundEnergy(CASE). The first set of questions to which DP&L objected was CASE's request for detailed information on all testing done on systems at Comanche Peak already turned over to operations, those which are in the process of being turned over, or those which are not turned ou r. CASE also asked for detailed information on Comanche Peak Unit I reactor coolant system hydrostatic tests, Integrated seek Rate Test, and Hot Functional Testing. CASE wants all workpapers, studies repor ts, analyses, etc., on any and all tests ever perfe med. DP&L argued that the information is extremely burdensome to produce, is remotely, (if at all), connected to the ratemaking issues in this docket, and that the thrust of this desired information is aimed at CASE's active intervention at the NRC hearings on the licensing of Comanche Peak. CASE argues that CASE and DP&L ratepayers h oe the right to know if their money has been, and will be, well-spent on Comanche Peak, and that the variety of information on the testing of the systems will provide background data which will help CASE formulate its case on the propriety of Comanche Peak costs at the ratemaking hearing. General Counsel argued that any items which are sought for pu*ooses of examining the prudency of expendituras or the management of the Comanche Peak operations is relevant to the proceedings and should be discoverable. As to this particular set of DP&L objections (CASE RFI's #6-12), the examiner overrules DP&L's objections, although reluctantly. Mr. Zeppa of the General Counsel's staff vouched on the record generally for the good faith of CASE. Therefore, the examiner will presume outright that CASE is not merely gathering informa' tion at this Commission for use at the NRC. Even if this were so, as long as the inforc:ation is relevant here, CASE's use of it at the NRC, 'as long as the data 11 not subject to a protective order, would be of no concern to the Commission. The real inquiry here must be: Is the information relevant to this ratemaking proceeGing? The answer is yes, as explained below. CASE's interest in these RFI's was roused by testimony provided by DP&L witness Michael Spence. Mr. Spence speaks in general terms of the successful testing done on Comanche Peak Unit 1, which is very near completion. It seems to the examiner that CASE has a right to see, in detail, any dccuments which relate in any way to tests at the plant, not just the final successful test.
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w. Docket No. 5256 Page 2 The documents are relevant in terms of the general issue of ;;rudency of expanditures at the phnt. Results of past tests may lead to some conclusions r whether OP&L ratepayer dollars aave been well spent at the plant. This impacts the issue of CWIP and is relevant to the issue of the amount the Commission should ultimately allow to be capitalized for Comanche Peak, which may be addressed now, or at some time in the future. It must be untioned at this point that the estimated cost of the Comanche Peak Project at present is $3.44 billion. The Texas Utilities Syste (TV) portion is $2.938 billion, or $1454 per kw. DP&L is responsible for 18 1/3% of this amount. Total CWIP proposed for inclusion in rate base here is $503,491,678. The examiner reluctantly overrules DP&L's ob.iections because CASE's requests do appear very burdensome. Therefore, to ameliorate the proposition of the copying of thousands and thousands of pages by DP&L, the examiner will allow DP&L to make these documents available at a central location accessible to CASE. An employee should be made available to provide assistance to CASE in its study of these documents. - In RFI #20 CASE asked for the details of the training programs f.,t- operational personnel at Comanche Peak. Again, CASE claims that this information is cost-related because CASE and DP&L ratepayers have the right to know that their dollars are being well-spent in terms of the efficient and safe heration of the plant. The examiner is unsure if training expenses are included in CWIP in this case; the ratefiling package does not detail the amounts which make up CWIP to that extent. Therefore, since the possibility exists that training expenses may be included, analysis of the training program by CASE in terms of its economic impact on rateoayers can certainly not be ruled irrelevant to the issues in this docket at the present time. CASE RFI's #34 and 35 request details of costs of the NRC evidentiary hearings, including a breakdown of the costs (legal fees, hotelflodging costs, etc.). Once again, to the extent these costs may be included in CWIP, or may be included in the ultimate amount requested to be capitalized for Comanche Peak, the information is relevant. I ! RFI #77, 78 and 108 again ask for detailed information on expenses incurred by Texas Utilities and DP&L at tae NR - Comanche Peak hearings. This information is relevant for the reasons stated immediately above. l The examitier is also of the opinion that this information (#20, 34, 35, 77, 78 and 108) should be made available to CASE, if it is in readable and understandable form, at a central location. DP&L may also, at its discretion, restate this information on separate schedules for CAI., if it deems appropriate. I
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--' Docket N). 5256 Page 3 From all of the above, DP&L's objections to CASE's RFI #6-12,18, 20, 34, 35, 77, 78 and 108 are hereby OVERRULED. DP& may make the information which responds to these RFI's available at a central location accessible to CASE.
ENTERED at Austin, Texas, on this the JA2 day of August,1083. PUBLIC UTILITY CO MISSION OF TEXAS
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ANGELA DEMERLE WILLIAM 5 HEARINGS EXAMINER tb i e k i
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9/24/83 4 DOCKET -NO. 5256 APPLICATION OF -l BEFORE THE PUBLIC UTILITY DALLAS POWER & LIGHT COMPANY C0tNISSION OF TEXAS FOR A RATE INCREASE . i CASE'S SUPPLEMENTARY MOTION TO COMPEL APPLICANT TO PROVIDE PHOTOCOPIES OF DOCUMENTS BEING MADE AVAILABLE TO CASE AT CPSES IN RESPONSE ':. ' TO CASE'S 'RFI'S ~NOS. 6-12 'AND 20 - NOW COMES CASE (Citizens Association for Sound Energy), Intervenor herein, and files _ this, its Supplementary Motion to Compel Applicant to Provide Photo-a copies of Documents Being Made Available to CASE at CPSES in Response to CASE's RFI's Nos. 6-12 and 20. 4
Background
On September 12, J983, CASE filed its Motion to Compel Applicant to Permit Photocopying of Documents Being Made Availa ble to CASE at'CPSES in Reponse to CASE's RFI's Nos. 6-12 and 20. In a prehearing conference call on September 70, 1983 (set oh Mondaf, September 19 to discuss'its 9/12/83 Motion to Compel and its 9/12/83 Motion to Compel Applicant to Supply Complete Information and Answers l to CASE's First Set of Interrogatories and Requests for Inforn.ation from Applicant), CASE's representative and Applicant's representatives discussed the granting of a protective order on the material at CPSES to which CASE had been granted access in the 8/22/83 Examiner's Order Ruling on DP&L's Objections to CASE's FRI's. CASE had no knowledge of Applicant's request for such protective order prior to the 9/20/83 conference call and was, in fact, put in the position of
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having to argue against the protective order before Applicant evcn presented its grounds for the issuance of it (such grounds being that CASE might use the i~nformation obtained in the operating lit. ease hearings for Comancha Peak). The conference call ~was exceedingly brief and was not recorded. In addition, ,
. Applicant's responses to CASE's motion on more complete answers.were also l briefly presented and orally ruled upon. Subsequent to that oral ruling order- ; * : x f.mw; w m ,.
ing the granting of a protective order, the Heanag Examiner has held the order _ - - _ , __ __. __ _ ____.__ _ -_.~.._.. _ _ .._ _ _..-___ __.__ _ __. _ _ _
Dock:t No. 5256 CASE'S SUPPLEMENTARY MOTION TO COMPEL PAGE 2 without signing it, pending the prehearing conference set now for Thursday, Septem-ber 29. At this time the issues of copying and of the possible granting of a pro-tective order on this material will be argued by the parties. CASE'S ' REQUEST CASE hereby requests that; Applicant be compelled to provide CASE with a com-i plete copy of each of the requested'pages of documents appeariag on a list that CASE i will hand-deliver to DP&L on Monday morning. Applicants should .be esmpelled ~to provide.a complete computer printcut of the Master Punchcard List as up-to-date as possible.1 (It is CASE's understanding that a computer printout of this docwent will be easier to run and cheaper to run than xeroxing the docment.) CASE further requests that Applicant be compelled to provide CASE with all of these documents at the beginning of the prehearing conference which is set for Thursday, September 29 at 10:30 a.m. in Austin. (It'.is CASE's understanding that in order for CASE to argue that it is entitled to such copies under the rules,for discovery that these copies need to be at the prehearing conference. Also, should , the Hearings Examiner rule in CASE's favor, CASE's represent &tiveiwould need to return to Dallas upon the close of the prehearing conference with the copies in hand in order to use them in preparation for cross-examination and to make the requisite number of copies to enter into evidence on Monday.) CASE intends to generate a summary 2 of the lengthy (approximately ?,500 page) computer printout, listing deficiencies, reworks, etc. by system. CASE intends l 1 When CASE's representative and an assistant viewed documents at the site on 9/22, they were told that the Master Punchcard Li.st which they werd shown went only [ through 5/25/83--and that this vas the most current list available. Based on other information, it is CASE's belief that many problems have come to light at the plant since 5/25--and it is also CASE's understanding that the punchlist should be more current than 5/25- .i.e. it should be almost current. If Applicant insists that the l latest, computer run goes only through 5/25, CASE requests that Applicant be compelled ! to provide CASE with a sworn, written statement to that effect on 9/29 at the pre-I hearing conference.
? CASE's representative', Mrs. Juanita Ellis will begin this sumary on Monday, 9/26 in the DP&L offices in Dallas.
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' DOCKET NO. 5256 ..
CASE'S SUPPLEMENTARY MOTION TO COMPEL : PAGE 3 to request Applicant ..ito stipulate to the accuracy of that sumary on Monday, -
~ October 3 at the beginning of the hearing. (It is CASE'.e understanding as well that CASE can submit a summary of a document into evidence only if the copy of the entire document is available at the hearing for the other parties to review.
1 hen, if anotheh p' arty:so desire it may move tha't the entire document, instead of CASE's prepared summary, be adnitted into evidence.) CASE feels that this document is esseritial as it delineates many (butenot all) of the problems whic5: are costing the ratepayers money--money which they should not have to pay in this or any future rate request by the Corapany. CASE'S RIGHT TO COPIES In addition to the reasons that were listed in CASE's 9/12.' Notion to Compel-Applicant to Permit Photocopying of Documents Being Made Available to CASE at
. CPSES in Response to CASE's RFI's Nos. 6-12 and 20 (see pages 3 and ff.), CASE would offer the fellowing additional reasons why it is entitled to copies of the requested documents by the rules:
- 1. The infonnation contained in these documents is relevant in these proceedings.
This is the central issue: either the documents are discoverable here or they are not. Clearly, as is stated in the Examiner's Order Ruling on DP&L's OtMections to CASE's RFI's (8/22/83) on page 1:
"Therefore, the examiner will presume outright that Ct.SE is not merely gathering information at this Coninission for use at the NRC. Even if this were so, as long as the information is relevant here, CASE's use of it at the NRC, as long as the data is not subject to a protective order, would be' of no concern to the Comission. The real inquiry here must be: Is the infonnation relevant to this ratemaking proceeding? -
The answer is yes, as explained below." (Emphasis added.) On pageb2 df the same order, the examiner continues:
"The documents are relevant in terms of the general issue of prudency
! of expenditures at the plant. Results of past tests may lead to some conclusion on whether DP&L ratepayer dollars have been well spent at the plant. This impacts the issue of CWIP and is relevant to the issue of the .
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DOCKET NO. 5256 i
, CASE'S SUPPLEMENTARY MOTION TO COMPEL PAGE 4
/ amount the Commission should ultimately allow to be capitalized for
/ Comanche Peak, which may be addressed now, or at some time in the the future." (Emphasis added.)
CASE simply notes that problems cost money to solve; reworks cost: money, redesign costs money, reconstruction costs money. If the ratepayers are ex-pected to bear the burden of any or all of these problems being corrected, then the ratepayers have a right to know what they are being charged for and how , much it is costing them.
- 2. The fact that CASE might also' choose to use any or all of this information in the continuing NRC operating licensing hearings for Comanche Peak is irrele-vant. As the Examiner has already stated on page 1 of her 8/22 order:
/ "Therefore, the examiner will presume outright that CASE is not merely gathering information at this Commission for use at the NRC. Even.it this were so, as long as the data is relevant here, CASE's use of it atrthe NRC, as long as the data is not subject to a protective order, would be of no concern to the Commission." (Emphasis addcd.)
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CASE, as the only remaining Intervenor in the operating license hearings for Comanche Peak before the U. S. Nuclear Regulatory Commisbion, has an l obligation to report anything which we believe may detrimentally affect t the public health and safety. Further, we are under a continuing Board
. Order. (as are all parties in those proceedings) to report to the Atomic Safety and Licensing Boud anything which we believe may be significant pertaining to the matters under consideration in those hearings. For example, in a Board Order dated January 4,1983, the Board stated, regarding a CASE exhibit, the decision by the Department of Labor Administrative Law Judge that Charles Atchison had been fired illegally by Brown & Root for reporting nonconfoming conditions at Conanche Peak:
' "Such decision contains important additional evidence directly connected j with testimony already in our record. In fact, we are surprised that only the Intervenor called this matter to the Board's attention on December 14, 1982 and filed a copy on that date. We have previously admonished both the Applicants and the Staff that they Nye an affirma-tive duty to infom the Board promptly of new facts or developments.
/12/ (Footnote /12/ Order dated October 20, 1981.)" s
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DOCKET NO. 5256 CASE'S SUPPLEMENTARY MOTION TO COMPEL PAGE 5 The responsibility tc, report any matters which are potentially significant was again confirmed in the Licensing Board's 9/1/83 Memorandum and Order.(Footnote 31, We are attaching copies of the Licensing Board's Orders of January 4,1983, and September 1,1983. It should be noted that CASE has attempted to keep separated the operatin'g license hearings and the;DP&L rate hearings for the most part, and we had 2 planned to introduce into evidence and question Applicant's witnesses regard-ing only a handful of documents from the operating license hearings. However, Applicant's co.ntinual allegations that CASE only wants documents in the DP&L rate hearings in order to use them in the operating license hearings for Comanche Peak forces us to bring these matters to the Hearing Examiner's attention. . Applicant would have CASE gagged from reporting any potentially significant matters discovered during the rate hearings -- cagoed from reporting them to the very agency (the U. 5. Nuclear Regulatory Commission) which has been mandated by Congress to protect the public health and safety and to see that nuclear-power plants are designed and constructed in such a manner that the public ! health and safety will not be jeopardized. l l CASE submits that Applicant's efforts in this regard are for one purpose and one purpose only -- to protect Applicant's from having to deal with deficiencies l in management for which they should have, to answer in these proceedings, while at the same time assuring that they will not have to deal with those deficiencies
- in the NRC operating license hearings for Comanche Peak.
To place CASE in such an untenable position is bad enough. However, to attempt to make the PUC a party to such unnecessary, illogical, and perhaps even illegal withholdir.g of information from the NRC is even worse, and CASE urges that the Hear'ing Examiner and the PUC not fall for Applicant's ploy and thus become a i party to such a questionable and perhaps even illegal maneuver.
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00CKE1 N0. 5256 CASE'S SUPPLEMENTARY MOTION TO COMPEL PAGE 6 CASE simply cannot both comply with the proposed Protective Order and at the same time fulfill its obligations as an Intervenor in the operating licensing hearings for Comanche Peak. It is grossly unfair to ask that we attempt to do so. Futher, Applicant has not and cannot show adequate grounds for a protective order, because norsuch grounds exist. Applicant has ignored the fact that CASE was an Iritervenor in all DP&L rate hearings since 1974, locally before the PUC was formed and iri every rate case after-wards. This was some five years t.efore we were accepted as an Intervenor in the operating licensing hearings for Comanche Peak. Thus, it is clear that our concerns regarding rates predates our intervention in the operating licensing hearings; and a review of the record of those earlier rate hearings reveals that we have actively participated in all of them--not only regarding Comanche Peak but also regarding other areas such as rate structures, etc. Although we have been forced to severely limit our participation in the present DP&L rate case because of our other comittments and will have to concentrated on the one area about which we have more knowledge than probably anyone else in the State (even the PUC)--Comanche Peak--our concerns regarding rates and rate-setting are still as great. In conclusion, CASE should not be penalized and placed in such an untenable position because we are crocerned not only with rate-setting but also wIth public health and safety. There are two distinct and separate forums for express <ing these I concerns--the PUC for rate-setting and the NRC for publi: health and safety. The PUC should not be a party to assisting the Applicant to hide any safety-related problems which may be uncovered during discovery in these proceedings--problems which (if ur. covered) should properly oe called to the attention of the Atomic
._ Safety and Licensing Board of the Nuclear Regulatory Commission in order to safe-guard the public health and safety. Nor should the public be kept from knowing how much any repairs, redesign, modifications, reconstruction, etc. are costing th em.
DOCKET NO. 5256 CASE'S SUPPLEMENTARY MOTION TO COMPEi PAGE 7' Additional Arguments Against the Granting of a Prutective Order on Documents In ad.iition to the arguments against the granting of a protective order on these disccvery documents in CASE's 9/12 Motion to Compel Applicant to Permit .I Photocopying of Documents Being Made Available to CASE at CPSES in Response to CASE's RFI's Nos. 6-12 and 20--and in addition to those argtnents given on pages 3 and following, CASE would offer the following additional reasons why such a protective order on this material should not be granted: 1 1 Applicant has shown no good cause nor proper g,'oundt for the granting of a , protective order. According to Risle 186b of the Texas Rules of Civil Procedure (1981 edition) it states that:
" . . . that secret processes, developments or research need not be disclosed, or . . . to protect the party or witness from undue annoyance, embarrassment, '
oppression, or expense." At no time did Applicant cite any of the reasons listed above for the reason for granting their request for a protective order--either in the August I 18 prehearing conference in discussing objections to these RFI's, or in any written motion following the Hearing Examiner's 8/22 order, nor in the prehearing conference call of 9/22. They merely reiterated the same assertion which was ruld against by the Hearings Examiner in her 8/22 order that CASE intended to use the information in the NRC operating licensing hearings--and that it would l te too burdensome to produce.. (See Order dated 8/22, page 1.) The argument regarding relevancy and irrelevancy is covered in this motion on prior pages. The argument regarding cost is covered in our 9/12 motion. (And, I l it should be noted, the cost of a computer run of the printout desired is supposed to be much lower than the cost of xeroxing it.) While it may wel:1 be annoying , l for Applicant to have to produce these copies--or even moreso, embarrassing--these reasons hardly have bearing in a hearing regarding rates when the Applicant is l - a corporation--not anyindividual.
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DOCKET NO. 5256 CASE'S SUPPLEMENTARY MOTION TO COMPEL PAGE 8
,N or is the information or the documents proprietary in nature. These are not secret " processes, deve'lopments, or reseanth." These are tests and lists of tests and reworks, etc. It is neither patented nor a trade secret.
Nor, since DP&L and its sister companies are regulated monopdlies with rgt competition in its service area for electric service (unlike Southwestern Bell who has competition in the long-distance area from other companies), does the idea of commercial information that would be of use to competitors apply here. Applicant has not stated in any forum or motion or answer to any of these RFI's regarding these documents that the problems associated with these tests, etc. are associated with costs which are being capitalized--and thus do not appear in this rate filing package'. Therefore, CASE and the other parties to this pro-ceeding must assume that these costs for modifications, reworks, etc. cict appear in this rate request--and that, therefore CASE has the right to these copies and the public aas the right to know about the information therein--without the gag of a protective order being placed- on them.
- 2. Applicant's request for a protective order is illogical. Not only does Appli-1 cant have no sh'owing of good cause for the issuing o'f such an order, their request would be humerous if the issue were not so serious.an attempt to block the ratepayers from knowing vital information related to the amount of CWIP being requested in this hearing.
By their contorted logic, Applicant's are requesting thatthe very documents cited by their own witness, Mr. Spence, as evidence proving Apolicant's case in prefiled testimony (which is itself public record) be placed under this protective o rder. Therefore, if CASE were to have to cross-examine Mr. Spence on these documents in the hearing, it would have to dn so sealed from public view if such an order were granted--but.his testimony characterizing them would not! ! In addition, Applicant's request raises a point of simple logic: If the
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DOCKET NO. 5256 CASE'S SUPPLEMENTARY MOTION TO COMPEL PAGE86, tests are indeed proof of Applica^t's position, then surely Applicant's would want to ensure that the tests and the test results be made public. If they are evidence for Applicant's position, why would Applicant wish to hide them? In addition, if the tests are what Applicant claims them to be--how could CASE
. possibly use them to support its contention in the operating licensing hearings of shoddy workmanship, improppr engine';?ing, etc. in the NRC hearings? For, if the tests are indeed OK, they could.not possibly pruve CASE's contentions and CASE could not use them there.
Only if the tests are not alright--only if there are indeed, problems either in the tests themselves or problems uncovered during the tests does Applicant's request begin to make sense. Only if the tests do not prove Applicant's points would Applicant's then seek to keep them from public view! And only if the tests are not alright could CASE use them to advantage in the NRC hearings. Therefore, if Applicant's insist that these documents not be made public and ~ that a protective order be granted, the general public is free to speculate tnat these tests do not support Applicant's position, but may, in fact, contradict i t.
- 4. The request for the granting of a protective order is untimely. As of the date of the Hearings Examiner's 8/22 Order Applicant; chad not filed a motion teouesting a protective order on this material. Nor did Applicant ask for one on this information during the prehearing conference of 8/18. (Applicant did, however, arg'ue that the contracts requested by CASE in RFI No.114 were proprietary in nature and that they would move for a protective order to be granted on them. Therefore, CASE rewrote' RET No.114 to avoid the necessity .
of signing such a protective order.) Nor did Applicant file a motion for a protective order upon receipt of the Hearings Examiner's 8/22 order--the logical latest time for them to have done so.
DOCKET NO. 5256 CASE'S SUPPLEMENTARY MOTION TO COMPEL PAGE 9 No, nor did Applicant file for such an order prior to CASE's representatives first visit to the plant to view the documents in question. When CASE's representatives viewed the documents on 9/5'(and again a 9/22) they were not under~ any protective order. CASE- could have called a press conference based on its notes of at least the first day of viewing documents there witaout having violated any~ order. CASE believes that Applicant is attempting to get such pro-tection retroactively. Nor can Applicant argue that there is any qualitative differenca in the documents which CASE's representatives viewed.on either day--nor of any which they have not yet viewed. It was only upon learning that CASE had filed and mailed on 9/12 its Motion to Compel regarding photocopying that Applicant apparently verbally indicated its intent to request a protective order on the docunents from the Hearings Examiner. Quoting our 9/12 Motion on photocopying CASE reiterates its respnse to this: , "If Applicant chooses to do so now, it merely highlitjhts Applicant's attempt l (to) prevent this information from being presented in this hearing and from i being placed under the scrutiny of its ratepayers. CASE's reply to this calculated foot-dragging on this essential data is: What does DP&L have to hide?"
- 5. CASE is a citizens' group. As a citizens group comprised wholly of l volunteers, CASE has long been concerned with the public's right to know. CASE has avoided becoming entangled in protective order agreements in the past (even in i
i this very hearing on RFI No.114), feeling that the public's right to know that 1 which affects it either in its pocketbook or regarding its safety and health is paramount. CASE has always been primarily concerned about informing the public ! of the problems ar;d the associated costs of those problems at Comanche Peak--thus l we would oppose any curtailing o'f the public's right to know what they are paying l for and why. , l
c . . DOCKET NO. 5256 CASE'S SUPPLEMENTARY MOTION TO COMPEL PAGE 10
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CASE feels that Applicant has a history of denying the existence of problems at the plant--much less the existance of the costs associated with selving those ! problems.~ CASE needs these docisnents--copied and accessible to the public-- to establish the existence of those problens in the 'public record; only then can i i CASE move on to establishing the costs of these reworks, redesigns, etc. Each redesign, each rework, etc. has a corresponding pricetag attached. The public needs to kno# what these are. . I CONCLUSION For all of the reasons listed in this motion and in CASE's 9/12 Motion to l Compel Applicant to Permit Photocopying of Documents Being Made Available at. CPSES to CASE in' Response to RFI's Nos. 6-12 and 20, CASE requests that Applicant i be compelled to:
- 1. Provide CASE with a complete copy of each of the requested pages of ,
- documpnts appearing on a list which CASE will handdeliver to DP&L on Monday morning, September 26 (and will mail to all parties the same day)--including
- a complete computer printout of the Master Punchcard List as up-to-date as pcssible. .
- 2. Provide CASE with all of the documents listed in Item 1 above at the beginning of the prehearing confernence on Thursday, September 29 at 10:30 a.m.
2 ) CASE would also request that Applicant's request for a protective order be
' denied. .
Respectfully submitted, . hfA k' b L(Ms.) Barbara N. Boltz, Boardmember CASE (Citizens Association for Sound Energy 1426 S. Polk. - Dallas, TX. 75224 ' i (214)339-4979 (home); (214)243-6191, ext. 521 (work) Dr. David H. Boltz, Boardmember
. .. v CERTIFICATE OF SERVICE t
By my signature below, I hereby certify that a true and correct copy of CASEtC S&pve% /!w77ovy 7bcomnt affEiMo; /WMi04-t o rpmwhflof Dxum+#TT MIM #1806 /?vAct4MJs 47~ /Sfr in AMbut- /> CMG OAM i%c.wyza~ta / in Docket No. o256 was mailed this 42 9 day of S C , 1983, first class United States mail, except for the names marked (*) which were sent by ! Certified Mail, Rdturn Receipt Requested, to:
- Mr. Robert A. Wooldridge
! Worsham, Forsythe & Samples 2001 Bryan Tower, Suite 2500 Dallas, Texas 75201 Mr. Galen Sparks - Assistant City Attorney 7DN Dallas City Hall 1500 Marilla Street Dallas, Texas 75201 Peggy Wells Dobbins St.,Regis Corporation
' 237 Park Ave.
New York, New York 10017 Ms. Martha V. Terry Attorney for Texas Retailers Association Davis & Davis, P.C.. P. O. Box 1588 Austin, Texas 78767 ; Mr.~ Allen H. King Guleral Counsel Public Utility Commission of Texas 7800 Shoal Creek Blvd. Suite 400 N Austin, Texas 78757 Mrs. Juanita Ellis CASE - Citizens Association for Sound Energy 1426 S. Polk - Dallas, Texas 75224 (original) Ms. Angela Demerle Williams Hearings Examiner . Public Utility Commission of Texas 7800 Shoal Creek Blvd. Suite 400 N Austin, Texas 78757 f-(hkA ,/h - CASE Board Member , 2012 S. Polk Dallas, Texas 75224 [ _ 214/339-4979 214/243-6151, X. 521 (Ms. Boltz)
DOCKET NO. 5256 APPLICATION OF DALLAS l FUBLIC UTILITY COMPANY POWER AND LIGHT COMPANY I
- 0F TEXAS FOR AUTHORITY TO CHANGE I RATES I EXAMINER'S ORDER CONCERNING MOTIONS DISCUSSED AT PREHEARING CONFERENCE HELD SEPTEMBER'29, 1983 A Motion to Intervene was filed by Office of Public Counsel (OPC), represented by Jim Boyle. The Motion was granted.
The OPC also presented a Motion to Dismiss, which, af ter full argument, was denied, because the motion showed no legal reason why this case should be , dismissed. The OPC filed a Motion for Continuance which was also denied because the company refused to extend its effective date, and the case must therefore be heard at the present time to meet statutory deadlines contained in the Public Utility Regulatory Act (PURA), Tex. Rev. Civ. Stat. Ann. art. 1446c, 543(1980). v Finally, CASE's Motion to Compel, and applicant's Motion for a Protective Order were discussed. The Motion to Compel was granted. Applicant's Motion for a Protective Order was denied because applicant did not show good cause for entry of sitch an Order and because no showing was made that exception should be made to the provisions of Texas Open Records Act, Tex. Rev. Civ. Stat. Ann. art. 625217a(1981) which generally provides.for open access'to public records. The answers which are to be provided to CASE's RFI's are public records, and subject to the Open Records Act. Therefore, applicant's Motion is DENIEO. ENTERED AT AUSTIN, TEXAS on this the M day of Septerrn u , 1983. l O i PUBLIC UTILITY COMMISSION OF TEXAS
</Ik U lue ANGELA MARIE DEMERLE ADMINISTRATIVE LAW JUDGE l
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r TRANSCRIPT OF'PROCFEDINGS BEFORE THE PUBLIC UTILITY COMMISSION OF TEXAS AUSTIN, TEXAS IN THE MATTER OF THE APPLICATION ) OF DALLAS POWER & LIGHT COMPANY ) DOCKET NO. 5256 FOR A RA".' E INCREASE ) HEARING ON THE ME RI'J" BE IT REMEMBERED that at 9:30 a.m., on the 3rd day of October 1983, the above-entitled matter came on for hearing at the Offices of the Public Utility Commission of Texas, 7800 Shoal Creek Boulevard, Suite 450-North, Hearing Room A, Austin, Texas 78757, before the HONORABLE ANGELA MARIE DEMERLE, Hearings
, Examiner; and the following proceedings were reported I
k) by Court Reporters of: l l l l Vol. I Pages 1-337 l KENNEDY REPORTING SERVICE, INC. l 7800 Shoal Creek Blvd., Suite 346-W Austin, Texas 78757 y, (312) 438-3297 /
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l 4Wu 1anner uross tu. 1 A. For actually buying it, no; but getting permits { o
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p-y 3 In other words, if you can't use it, why buy it? 1 4 G Well, say, buying a -usable site? Do you know any I i 5
!l fact that would prohibit you fr'om buying c usable site?
6 l A. Yes, getting the permits approved for the air and i I water pennits would be a potential problem. i 8 MR. SLOCUM: We will pass the witness. 9 DEMERLE: I think that is it. Thank you, 10
) 11r. Tanner.
I 11 Are there any objections to his being excused? 12 I (Witness excused. 13 14 ' MICHAEL D. SPENCE 15 i was called as a witness on behelf of Dallas Power & Light 16 Company anJ, being first duly sworn, was examined and 17 r's testified as follows: i..,) 18 DIRECT EXAMINATION 19 BY MR. WOOLDRIDGE: 20 G State your full name, please, sir. 21 A. Michael D. Spence. l 09
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i G Mr. Spence, have you prepared pre-filed direct i 93 testimony, which is reflected under the tab marked "Spece" , og
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4 es in DP&L Exhibit No. 2? I ) v , j
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j A. Yes, sir, I have. ' KENNEDY REPORTING SERVICE INC. 7800 SHCAL CREEK BLVDe 346-W i AUSTIN TEXAS 78757
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spence - Cross B4 m 1 BY DR. BOLTZ - 2 g Ckay. Mr. Spence, in the upcoming reorganization,
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\_) 3 what position will you hold? .
4 A I will be the President of the Generating Division 5 of Texas Utilities and Electric Company. I 6 g In reading your vitae, I don't see that you have 7 ever been employed by DP&L. Have you ever been? 8 A No, I have not. 9 G Since you are nat, how did Dallas Power & Light 10
.( ) decida to have you give the update on Comancne Peak? Why 11 did they choose you?
12 A Because of my current organizational responsibilities 13 with regard to Comanche Peak. I am President of TUGCO, 14 currently, which is the licensee. 15 g Okay. And what would your relationship be to 16 Dallas Pcwar & Light? 17 A 3 Now? 18 g I guess I am regarding in terms of interface. You I 19 are not part of them, but you deal with them. Is that correct? 20 A
- Yes. TUGCO is agent for Dallas Power & Light, 21
! Texas Power & Light and Texas Electric Servic1 Company in the 22 construction cnd operation of Comanche Peak', as well as in 23 the* operation of other lignite facilities around the state. 24 . O So in a sense, you are indirectly employed by
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25 Dallas Power & Light, if you are their agent? KENNEDY REPORTING SERVICE INC. 7800 SHOAL CREEK BLVD.- 346-W AUSTIN. TEXAS 78757 (5 t ?) 4%TQ7
Soonce - Cross l34 isl4 m 1 % That is just the report, and not the inspection. 2 Am I correct? i /7 6 k') 3 A I am not sure what inspection you are talking about. 4 G The independent assessment. 1 5 A That is the report on the-rezults of his independent! l 6 assessment. i 7 0 Okay. You should have a copy of a letter in front 8 of you. , 9 I am about to place one in front of you. The n 10 pertinent identification is up in the upper left-hand corner. (s -) 11 Is that 8332? 12 A It is apparently referring to Docket 50-44 5/83-32. , 13 C Okay. I would like to call your attention to the l l 14 last page of that, page 8. Have you seen that page before? j 15 A No, sir. i 16 % In your testimony you talked about plant systems I 17 being turned over, and then you talked about a number of
~T l (V 18 s ncessful tests being completed.
I l 19 Page 8 basically gives an overview of all of the l 20 tests done and tests yet to La done. Am I correct? 21 A. Well, page 8 refers to manning status, refers to 22 plant testing status. 23 G Could you please briefly describe what an acceptance 24 test is? a () 25 A Yes, sir, if I could get my notes. XENNEDY REPORTING SERVICE INC.
! . 7800 SHOAL CREEK BLVD. 346 W AUSTIN. TEXAS 78757 (512)458 3297
135 Spence - Cross iB15 m 1 The question was to describe u. acceptance test? 2 G Yes, sir.
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3 A. An. acceptance test is one form of test that we are 4 performing at Comanche Peak. The other type of test is a pre-5 operational test. 6 G I was wondering if you could explain the difference 7 between the two?
- 8 A An acceptance test is the kind of test that we L
9 would normally perform on components or systems within a non-() v to nuclear, a fossil-type power plant. q 11 And this means that the individual components and 12' their performance would be varified as to their operation, 13 and, then, the system would be placed into service to provide 14 initial system operation.
, 15 There are no formal verbatim procedures required by
- I 16 NRC regulations to perform an acceptance tes', as they are i
m 17 required on a pre-operational test of a safety-related system. I k) 18 G Are acceptance tests-- 19 A Excuse me. I was not quite finished. I { 20 Mandatory plant testing is not required prior to i j 21 initial plant operation for those systems that require only nd T6 22 acceptance tests. 23 1 24 1 (O v 25 3 KENNEDY REPORTING SERVICE INC.
, , 7800 SH0AL CREEK BLVD. 346 W i AUSTIN, TEXAS 78757 (512)458-3297
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, DP&L 1 S Are acceptance tests done only on turned over 2 items or turned over systems?
q V 3 A. Yes, by definition, if a system has not been turned 4
! over from construction to startup-into operations, then 5
! startup in operations can't test them. They don't have 6 control.of it. 7 Could you please briefly explain what the term G 8 turnover means? f 9 A. Yes, sir. A turnover takes place when a system 10 or a subsystem within the plant has essentially completed 11 its construction phase and construction turns the 12 responsibility for that system over to startup in operations. 13 G Let's assume it's a system work done by Brown & 14 Root and they complete it. So when they turn it over they 15 give it to TUGCO., Is that correct? 16 A That's correct. . 17 ' Does this mean, then, that once it's turned over S 18 that all construction is finioned on that particular piece 19 of hardware or system? . 20 A. No. There may be a punch list on it, and after 21 the particular test that's required for that system, whether i 22 it be a pre-operational test or acceptance test, has been 23 performed, that test may identify additional construction 24 That's the reason you do the work that needs to be done. O 2s tese - 1e to ve1idete thee erstem's serfermeece ie eccore ece y KENNEDY REPORTING SERVICEINC: 7800 SHOAL CREEK BLVO.- 346-W AUSI'N. TEXAS 78757 (512)458-3297
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' .137 1pb2' scence - cross 1 with design specifications. * , 'l 2 4 I see. Is there some sort of criteria that TUGCO
- O 3 has that they,would feel that a system - '
4 Let me withdraw that. Let me say has TUGCO ever 5 rejected a system from a contract on the bacis of the test? 3.
- l- 6 A. You mean some Constructions craft?
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%. Yes, sir. ;
l-8 p .A. Yes, I'm certain that over the course of the 9 project there have been systems that Construction felt like O 10 were ready to be turned over.and'TUGCO wanted something I 11 else done on that system by Construction before it was 12 turned over, perhaps a valve handle was not as accessible ' 13 as the operator needs it to be so he can conveniently 14 operate the valve. 15
, % Is that, turnover -
IO MS..DEMERLE: Dr. Boltz, I'm sorry to interrupt, but this seems like an awfully general discussion ' 18 about operations-at the plant. Can you tell me how this 19
-is going to ultimately relate to the rate case?
I 0 DR. BOLTZ: Yes. I'm just getting to the 21' cost right now. You are anticipating me. o
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MS. DEMERLE: Go ahead. 23 DR. BOLTZ: You stole my thunder. 24 MS. DEMERLE: I hope not.
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O 2s KENNEDY PEPORTING SERVICEINC; 7800 SHOAL CREEK 8LV0e 346 W AUSTIN. TEXAS 78757 (512)458-3297
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Spence - Cross 138 1 BY DR. BOLTZ: . 2 O In dealing with these turnover operations, if
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3 TUGCO accepts it and more construction work needs to be - 4 f done, who pays the cost for that extra construction or 5 { repair? 6 A. I'm not cure what you mean by extra construction.
' g Well, let's say that we have Systen X and it's l:
j 8 turned over and the tests find that there are five orablems l 9 that need to be resolved and you have accepted it. Does in 10 t ) this mean, then, that TUGCO pays for it - for the repair 11 and rework as a normal construction cost? 12 A. Dr. Boltz, I'm trying to. answer you and I want 13 to be responsive, but you just introduced a whole new concept 14 that we haven't been talking about of rework and repair. 15 What I'm talking.about - you asked me, I believe, what is 16 turnover. 17 G Yes. 18 A. Turnover takes place when Construction passes a 19 system to Operations and says, " Here. We built it according 20 to specifications. It is now ready for you to test and to 21 operate." Occasionally, Operations will say, "Po, we're 22 not ready to turn it over because there is an adjustment
'6 23 ! that we would like you to make or modifications we want you 24 to make before we take responsibility for the system, because 25~ we don't have the capability to modify the construction.
I KENNEDY REPORTING SERViti. INC, 7800 SHOAL CREEK BLVD. 346-W AUSTIN. TEXAS 78757 (512) 458 3297
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*ypb4 ' Spence - Cross 139 1
That's your job, not ours." 'And I used in my example mayue 2 the accessibility to the valve in a piping system. Once j 3 ' that has been.taken care of to TUGCO's satisfaction, they - t 4 accept the system as being turned over to them and they 5 begin their tests, wilether it's a pre-operational test or 6 an acceptance test, as the case may be, dependinc on the - 7 i system. I 1 8 G And let's assume that these tests are being done 8 and we find out something that is drastically wrong with 0 the system that has been turned over and it needs expensive 11 repair. I2 Would a contractor assume those costs because they were 13 remiss in their construction, or perhaps a vendor inadvertently 14 was remiss, or does TUGCO have to pay those costs? 15
, A. It would depend on the nature of the work that 16 had to be done and what its cause was.
0 Let's talk about our valve. Let's say our valve 18
- was faulty and it wasn't caught in the operational test 19 or the acceptance test.
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A I,was not talking about a faulty valve. I was i
'l talking about a valve that maybe the operator, who is 5' 9" tall, can't reach a valve handle that is 6' 6" off the 23 ground. If they have built and designed to specs, but once
'"t it was physically in place it became obvious to all in my D-d ,3
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example that the valve needed to be moved down a little,.I KENNEDY REPORTING SERVICEINC; 7800 SHOAL CREEK BLVDr 34t, # 1 AUSTIN. TEXAS 78757 , (512)458 3297
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' _. Soence - Cross i wouldn't characterize that as a major problem. It's just n ,3 the type of event that occurs when you are involved in a
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%j 3 Everything doesn't fit all the major construction project. .
4 time. 5 ' G Okay. I guess my concern was is turncver an 6 cconomic term as well ac an engineering one? Is there a I point in time when TUGCO basically - I'm sorry. Go on ahead j 8 i and answer. 9 No, it is not an economic term. It is a technical A
,i (m__) 10 term used in the progression and the statusing of the 11 physical development of the project. It was one among a 12 number of tracking nechanisms we have to track progress.
13 The fact that we have turned over 90 percent of the systems I4 from Construction to Operations indicates the approaching 15 completeness of the construction procecs, as an example, I 16 as I testified to in my direct testimony. I- DR. BOLTZ: CASE uould like to submit this i (- -) V 18 document, 83-2, as evidence in this case, as Exhibit No. 6. i 19 MS. DEMERLE: This is the letter we were 20 previously talking about which refers to Docket No. 50-445 21 83-32. Are there any objections? 4.> Mr. Wooldridge, do you have an o5jaccioa? 23 No. MR. WOOLDRIDGE: 4 MS. DEMERLE: Anyone else? 25 (A) The letter will be admitted. KENNEDY REPORTING SERVICEINC; 7800 SH0AL CREEK BLVD.- 346 W AUSTIN. TEXAS 78757 (512)458 3297
,. . - Spence - Cross 150
-2M3m 1 associated with that. .
2 4 And this has to be retosted? Tnat is what that says? 3' A I don't know whether-it has to be tested or not. . 4 O The steam generator No. 2 requires rehydro. That's
'S a test? I 2
- 6 A Assuming that--
i . 7 MS. DEMERLE: That's on the 9--on both reports, j 7,
,right?
i . 9' THE WITNESS: Yes, f (} 10 0 What would be the cost of a review test? Do you 11 happen to know? ' 12 A No, sir. 13 G Okay. Isn't it true that the nuclear industry is 14 having problems with the steam generator of the same type as 15 was planned to be used at Comanche Peak? 16 A Yes, sir. There have been some problems with the 17 Westinghouse steam generators. O 18 G Isn't it true that you are going to be required to 1 19 either modify or run the generator at only 70 percent of power 20 if the modifications can be done? l 21 A The modifications have been done, l 22 4 They have been done? 1 23 A Yes, sir. t 24 Q When were they done? (} 25 A In July and August, I believe. Modifications to ! XENNEDY REPORTING SERVICE INC. 7800 SH0AL CREEK BLVO. 346 W
- AUSTIN. TEXAS 78757
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Soenca - Cross 151 9-2M4m 1 oliminate the tube vibration in the steam generation in turn 2 was done in the summer of '33. I) - 3 I quite frankly have forgotten the exact date becaute-4 it was in the June, July, August time frame. About 120 tubos i
; 5 per steam generator were expanded to reduce the vib ation. l l
6 l G Was that done under a warranty? 4 7 A It was done by Westinghouse under warranty, i 8 G Does this now mean that the plant no longer has l 9 that 70 percent restriction on it?
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's 10 A Theplantneverdidhavethe70percentrestriction.l
[ 11 G Never did? j 12 A Well, if we had not addressed the tube vibration 13 problem, there is some reason to suspect that NRC would have i , 14 put some ? imitation on our operating license, but we were able 15 to address the problem, get an engineering fix and fix it in I 16 l the field before we received a license. l L7 Now we expect a supplemental safety evaluation l i
'-' 18 report from NRC just momentarily that signifies that they are f
19 concurring with the fix. We reviewed it with them, technical l l
; 20 review of the modifications done.
21 G Isn't it true that this is the first generator-1 22 that's been so modified by Westinghouse? j i 2J A I'm not sure'if that's correct or not. I believe 24 there is a unit in Yugoslavia.
? ; 25 G Let me re-ask my question--first American unit?
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,1 ) KENNEDY REPORTING SERVICE INC.
j 7800 Sn0AL CREEK BLV0e 340 W
] . AUST!N, TEXAS 78757 ,j (512)458 3297 4
. . Spence - Cross 152 1-2M5m g A It may be. I'm npt sure it would be the first one 2 in operation with this modification, though. There are a
(, k- 3 number of others. . 4 The point that I wanted to conclude my answer with 5 is the resolution of the tube vibration problem which was 6 identified in Westinghouse steam generators is not going to 7 have an impact on Comanche Peak, either cost-wise, schedule- , 3 wise, or any limitation on operations. 9 G It almost sounds like I have your personal guarantee (~'g to that we can expect it to run at more than 70 percent capacity? (J 11 A I have my testimony here for this proceeding that 12 we have addressed the problem and have resolved any reason for 13 low limitation from the steam generator tube vibration. 14 4 By what capacity do you expect Comanche Peak to 15 run at? 16 A What capacity? 0 Yes, sir. ; 1,7 18 A In terms of capacity factor? J 19 O Uh-huh. 20 A Well, the average for Westinghouse pressurized 21 water reactors with full loop systems similar to ours is in 22 the 60 percent capacity factor range. 23 Qaite frankly, I'm expecting TUGCO to do at least I that well with Comanche Peak, hopefully sotcewhat better. j 24 25 0 Let me just direct your attention to one other item I KENNEDY REPORTING SERVICE INC.
; 7800 SHOAL CREEK BLVD. 346 W AUSTIN. TEXAS 78757 (512)458-3297 ,
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Spence - Cross 153 1-2M6m on tnis punch list. 1 This is. item 477 S. 2 A Excuse me. Which list are we on?
.I} -($) 3 g On the ,9/23 list. -
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, A On the last page?
i 5 0 Second to last page. 6 A Lxcuse me. Would you tell me the item number, again? ' 7
.4 0477 S.
8 A' Okay. 9 4. And I will give you a second to read that. (} 10 Have you read it? r 11 A I read the descript' ion. 12 Yes, sir; I read it. I 13 % My question is: i What is TUGCO doing at this late l 14 date after the h'ot function test with a big hole in the pipe 15 in the main steam line? . q 16 A i Well, if you go over to the " Remarks" column, it 17
, would indicate to me that that has been repaired. I don't I
i ( 18 know when it was repaired, but I would have to assume it was 19 repaired before hot functionals. Otherwise, you would have j 20 lost all your steam out of the hole in the pipe. r 3 21 G I would agree with that, too,'excepc this is an open 22 punch list. 23 A Well, I'm not sure if it is or not. By and large, 24 I would suspect that most of the items on here are open, but l. (}
- 25 some may have been closed in the data base and not updated, KENNEDY REPORTING SERVICE INC..
7800 SH0AL CREEK BLVD. 346 W AUSTIN. TEXAS 78757 (512)458 3297 E _ . - ~ , - . _ . . . _ - , _ , _ . - - . , , _ . . _ _ _ _ . . . _ - . _ , _ . _ . _ - - . _ . . , _ _ . _ , _ _ . _ . . _ . _ - _ - _ - , _ - _ , -
Spence - Cross 9-2f17m 1 This'ono indicates it has been repaired. Is it on 2 this list?
,n V 3 % Yes, it is, where it says it's open. .
d fiS . DniERLE: Once again, Dr. Boltz, whether I I ' it's open or not is'of no concern to me. i 6 DR. BOLTZ: Well, if it's open it means that I 1
) 7 we are going to have not only a big expense of repairing it, l 8
but the hot functional test has to be redone. 9 MS. DEMERLE: About six months after the tests 7.s ( t 10 are run. 11 A If it's open, it just indicates that there's some 12 finish worx left to be done and in no way indicates any big 13 expense or repair work. That is a supposition. 14 g To repair something like that, would you have any 15 idea how much it would cost? 16 A. No, sir. l 17 G Do you keep track at all of cost of repairs done at 18 Comanche Peak? 19 A We keep track of the expenditures required to start 20 up and operate the project. 21 O But you have no records showing if something has 22 been reworked or repaired; you have no way of knowing what the 23 expense is? 24 A. Rework and repair is just a fundamental part of a () nj 25 massive, complex construction project like a nuclear power plant
, KENNEDY REPORTING SERVICE INC.
' 7800 SHOAL CREEK BLVD.- 346 W I AUSTIN. TEXAS 78757 (512)458 3297
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- i. Spence - Cross 155 i i-2M8m i or like a 40-story office building, or any other massive 2 phys'ical undertaking. There are going to be occasions where
('-') 3 human endeavor is involved that things, for whatever reasons, - 4 aren't dcne right the first time. And it would in no way be 5 supportive of the project to try to set up a massive accounting G systet.a just to keep track of what it would cost you to fix 7 something or change screething or modify something. ' side 2 4 8 So the ratepayers really have no way of knowing if 9 l there have been reworks that have been done and how much they l l ( 10 pay for them? i 11 A By specific item, ho, sir. 12 G Total by system? 13 L Well, the total -- I think the thing to put into 14 proper perspective is when the plant is completed, you look i 15 at the completed cost of the plant and compare that to the norm 16 as I have done in my testimony on page-- l 17 % I believe it's on page 10. g- . Ki're going to get that
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i 18 in a little bit. l, 19 A Well, if I could finish my answer to your question. 1 I l 20 The ultimate conclusion is the completed cost of the project. 21 And, based on its hich level status of completion I i 22 now, the anticipated completed cost of Comanche Peak based on i 23 current cost and schedules is well below the industry average
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,Q 854 LP&L - 5256 CASE ELMIBIT Citizens Association for Sound Energy Question #2, #3 Please give a complete, detailed listing of all systems at Comanche Peak which have not yet been turned over to operations.
' In regard to the systems referred to in question No. 2, please previde the current acheduled target date(s) for the turnover of ead. system which has net yet been turned over to operations.
The fol". awing was prepared under the direction of Mr. M. D. Spence, the sponsoring witness for this answer. Attached is a list of CPSES-1 systems which as of August 24, 1983, have not yet been turned over to operations. The target dates for these systems are also included. I J 9 1 e e ( y , - . _ , , , .---.,.-.,,----y - - - -- . .r. -ry-... -w. .m, , - . , . , - - . - , , , . p , -,,y
45 .y + 1 TARGET SYSTEM DESCRIPTION DATE l-OlDM EMERGENCY LIGHTING'lE & Non IE SEP83 1-02AM NC DISTRIBUT (SWI BLDG ROLL-UP DOOR) 1-02AM AC DISTRIBUTION 1-02AM AC DISTRIB (AUX BLOG ROLL-UP DOOR) 1-02AM AC DISTRIBUTION OCT83 - 1-0603 FIRE PROTEC (F.B. STNDPT & HOSE CAB) 1-0603 FIRE PROT. (AUX. BLDG., S.G. BLDG E.C) SEP83 1-0612 FIRE PROTECTION CONTAINMENT SEPS3 1-0613 FIRE PROTECTION MAIN CONTROL PANEL - SEP03 1-0705 CONTROL ROOM - HVAC, TORNADO DAMPERS SEPi-1-1201 COMMUNICATION SYSTEM AUGJ3 1-2603 CHILLER CIRCULATING WATER OCT83 1-3203 AUX. BLDG. TORNADO DAMPERS SEP83 1-3303 STM GEN. CHEM INJ & RECIRC SYS ' SEP53 1-3605 3AFEGUARD BLDG HVAC, TORNADO DAMPERS SEP33 1-4003 MANIPULATOR CRANE SEPS3
- l-4005 UNDERWATER LIGHTS SEPS3 1-4302 TURBINE OIL PURIFICATION SEP83 1-4903 CVCS CENTRIFUGAL CHARGING PUMPS SEP83 1-5502 RCP OIL COLLECTION SYSTEM SEP83 1-6402 REACTOR PROTECTION SEP83 1-6603 NULEAR INSTRUMENTATION SEP83 1-72201 TURBINE BLDG. ELEVATOR NOV83 1-7202 CONTAINMENT ELEVATOR NOV83
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2 TARGET SYSTEM DESCRIPTION DATE 1-7203 AUX. BLDG. ELEVATOR NOV83 1-7302 PROTECTION & SURVEILIANCE PAKG. N-16 OCT83 1-7433 NOVALLE INCORE t. FLUX MAPPING, RVIRS AUG83 1-8104 POLP,R CRAhE SEP83 1-8107 CONTAINMENT ACCESS ROTATING PLATFORM DEC83 1-8109 CONTAINMENT FUEL STORAGE CRANE OCT83 1-8201- METEOROLOGICAL MONITORING SEP83 1-8416 HEAT TRACING SEP83 1-8712 SECURITY FENCE SEP83 i l i l (
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.ASE EXHIBIT C55 DP&L - 5256 Citizens Asscciation for Sound Inergy Question #4, 4 1
2 Please give a complete, detailed listing of all systems at C0:.u.che Paak which have been turned over to operations. In r2garc to the systems referred to in question No. 4, please provide the date (s) that each system was turned over to operations. The 1:llowing was prepared under the direction of Mr. M. D. Spence, tne sponsoring witness for this answer. Attawned is a list of CPSES-1 systems which have been turned over to c;eratiors. The date of this turnover is also included. l e e
l 1 1 ACCEPTED SYSTEM DESCRIPTION DATE 1-0501 POTABLE WATER SUPPLY HEADER llOCT79 i l-0502- POT. WATER, TURB BLDG. & CONTROL RM 12AUG81 1-0503 POTABLE WATER 27JUL81 1-0601 SW INTAKE STRU. & 133 KV XFMR DELUGE 27AUG81 1-0602 FIRE PROTECTION UNIT 1 TG BLDG 29JUL83 1-0604 FIRE PROTECTION UNIT 1 DG BLDG '18JUN82 1-(605 FIRE PROTECTION (F.B., DELUGE SYS) 11JUN82 1-0606 FIRE PROTECTION 345 KV TRANS DELUGE 20MAY82 1-0607 FIRE PROT UNIT 1 MAIN TRANS DELUCE 20MAYB2 1-0608 FIRE PROTECTION HALON SYSTEM 30DEC82 1-0609 FIRE PROTECTION HALON SYSTEM 10DEC82 1-0610 FIRE PROTECTION HALON SYSTEM 10DEC82 1-0611 FIRE PRGTECTION PRIMARY GUARD HOUSE 20MAY82 1-C701 CONTROL ROOM - HVAC. A/C UNITS 29JUL81 1-0702 CONTROL ROOM - HVAC, KITCHEN 06FAYC 1-0703 CONTROL ROOM - HVAC, EMER. FILTRATION 19JUNBA 1-0704 COMPUTER RM & TSC AIR COND UNITS 09DEC62 l 1-0801 BATTERY ROOMS EXHAUST HVAC 03SEPSO 1-0802 UNCONTROLLED ACCES AREA VENT 22JUN81 1-0803 BATTERY ROOMS VENTILATION 14FEB83 1-0901 WATER TREATMENT 230CT79 1-0902 REVERSE OSMOSIS FOR MAKEUP 28AUG80 F 1-1001 DEMIN & RMVW 02JUN80 1-1002 DEMIN & RMUU 20APR80 i
2 ACCEPTED SYSTEM DESCRIPTION , DATE l-1003 DEMIN & RMUU 15JUL81 1-1004 DEMIN & RMVW 23SEP81 1~1101 COMP COOLING WTR 13MAY81 1,-1102 COMP COOLING WTR 18AUG81 1-1103 COMP COOLING WTR 16DEC81 1-1104 COMP COOLING WTR PIPING 08JUN83 1-1301 TB SWITCHGEAR AREA HVAC 10DEC80 1-1302 TURBINE BLDG HVAC 030tC80 1-1303 LUBE OIL RES. RM HVAC 02DEC80 1-1304 T. D. UNIT HEATERS 23JAN81 1-1305 T. B. STAIRWELL PRES FANS 12DEC80 1-130,6 TVR ROOM A/C 27APR81 1-1307 CAS ROdM HVAC OlAPR81 1-1308 ERF COMPUTER ROOM HVAC 30AUGS2 1-l' 401 INSTRUMENT AIR 13JUN80 1-1402 INSTRUMENT AIR 24.TPR81
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1-1403 INSTRUMENT AIR OJUL81 1-1501 UNIT #1 SER. AIR 13JUN80 1-1502 UNIT #1 SER. AIR OlJUN81 1-1503 UNIT #1 SER. AIR 24JUL81 1-1601 TURB PLANT COOLING WATER 04JUN80 1-1701 OFFICE & SERVICE AREA HVAC 27AUG80 l-1702 OFFICE AND SERVICE AREA HVAC 22JUN81 1-1901 MAIN CONDENSER 29MAY81 1
l 3 ACCEPIED SYSTEM DESCRIPTION DATE 1-02AH.5 UON-CLASS 1E UNIT 1 480V MCC's 14JAN80 1-02AI.1 CLASS lE 480V MCC's 03JUL80 1-02AI.2 CLASS 1E 480V MCC's 26JUN80 1-02AI.3 CLASS lE 480V MCC's 06MAY81 1-02AJ.1 CLASS lE 480V MCC's 03JUL80 i 1-02AJ.2 CLASS lE 480V MCC's 03JUL80 1-02AJ.3 CLASS lE 480V NCC's 23FEB81 1-02AK IE EMERGENCY LIGHTING AND POWER 22JUN82
'l-02AL NON-CLASS lE LIGHTING AND POWER 05JAN82 1-02AP CLASS lE INVERTERS 14FEB83 1-02AG INVERTER IVlCS & IVlC6 118 DIST 17JAN83 1-02AS TRAIN A ll8V DISTRIBUTION 17APR80 1-02AT TRAIN A'118V DIST SYS 26NOV79 l l-02AU 1 RAIN B ll8V INVERTERS 30JUN81 1-02AV TRAIN B ll8V D'STRIBUTION 14NOV79 l-02AW TRAIN B ll8V DIST SYS 16NOV79 1-02AX.1 MISC. 208/120/118 VAC DISTR. 230CT79 l l-02AX.2 MISC. 208/120/118 VAC DISTR. 03JAN80 i
1-02AX.3 MISC. 208/120/118 VAC DISTR. 18JUN81 1-02AX.4 MISC. DISTR. PNLS. 16 MAR 82 1-03SA 138KV S/U XFMR 17AUG79 l-03SB 345 KV TRANSFORMER, 6.9 KV CABLE 06APR81 ! l-0401 STATION SERV WTR 22JAN81 1-0402 STATION SERV WTR 10SEP81
4 ACCEPTED SYS'2Epj DESCRIPTION DATE l-8702 SECURITY CdMPUTERS 24SEP82 1-8703 SECURITY MULTIPLEXERS 1 & 2 060CT82 1-8704 SECURITY-CONTROL ALARM STAT. CONSOLE 24SEP82 1-8705 SECURITY-2NDARY ALARM STAT. CONSOLE 26JUL82 1-8706 SECURITY MULTIPLEXER 46 12NOV82 l l-8707 SECURITY MULTIPLEXERS 3 & 4 27DEC82 i 1-8708 SECURITY MULTIPLEXERS 7 & 8 llJAN83 i ! l-8710 SECURITY DURt:SS SYSTEM 26JUL82 l-8711 SECURITY PERSONNEL SEARCH SYSTEM 250CT82 l-8713 SECURITY RADIO COMMUNICATIONS 13APR83 l-8801 ANALOG CONTROL SYSTEM, BOP RACKS 09APR80 1-8802 ANALOG CONTROL SYSTEM, NSSS RACK 12 MAR 81 1-9101 LOOSE PARTS MONITORING 14JUN82 1-9301 CONTAINMENT ELECT. PENETRATIONS 29DEC82 1-9302 CONT. PERSONNEL AIRLOCK & EQUIP. 120CT83 1-9303 EQUIPMENT AIRLOCK & EQUIP. 23NOV82 1-9304 EMERGENCY AIRLOCK & EQUIP. 130CT82 1-8403 HEAT TRACING, TB HOSE STATIONS 270CT82 1-8404 HEAT TRACING, TG PRIMARY WATER SYS. 07APR83 1-8405 HEAT TRACING, MAIN STEAM 12AUG83 1-8406 HEAT TRACING, WATER TREATMENT 20MAY80 l l-8407 FREEZE PROTECTION THUW l 180CT82 l 1-8408 HEAT TRACING, SERVICE WATER 08JAN81 1-8409 HEAT TRACING, CIRCULATING WATER 14AUG81
5 ACC3!TED SYSTEM DESCRIPTION DATE 1-8410 HEAT TRACING, EXTRACTION STEAM 1SOCT82 1-8411 HEAT TRACING, POTABLE WATER 25JUL81 1-8412 HEAT TRACING,. HEATER DRAINS 12AUG83 1-8413 HEAT TRACING, CHILLED WATER 25JUL81 1-8414 HEAT TRACING, SURFACE H2O PRE-TREAT. 08DEC80 1-8415 HEAT' TRACING, TW HNAD TANK PIPING 06JANdl 1-8417 HEAT TRACING, TG EUC LINES 13 MAR 83 1-8418 HEAT TRACING, CVCS 06JUN83 1-8419 HEAT TRACING, BRS 11APR83 1-8420 HEAT TRACING, RADIATION MONITORING 15APR83 1-8421 HEAT TRACING, STEAM GEN. FW 06JAN83 8422 HEAT TRACING, PASS 12APR83 1-8501 CATHODIC PROTECTION, TURB. BLDG. 195EP78 i 1-8502 CATHODIC PROTECTION, Chi & N. YARD 26MAY81 1-8503 CATHODIC PROTECTION, S. WEST YARD 16 MAR 81 1-8504 CATHODIC PROTECTION, SWI & SW YARD 27FEB80
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l l-8701 SECURITY (UPS) 22SEP82 1 1-7705 POTABLE WATER OlAUG77 1-7706 FIRE PROTECTION OlAUG77 1-7707 POWER DISTRIB TO SHOP EQUIP OlA;37 ~i 1-7708 SERVICE AIR PIPING G1AUG77 1-7709 GANTRY CRANE OlAUG77 1-7710 ANNEX BLDG OlAUG77
-1~7801 ERF COMPUTER 16AUG83
6 ACCEPTED SYSTEM DESCRIPTION DATE l-7802 ERF COMPUTER CABLES 08JUL83 1-8001 SEISMIC INSTRUMENTATION 05APR83 1-8101 TURB BLDG GANTRY CRANE 26MAY83 1-8102 FUEL BLDG. OVERHEAD CRANE 20APR83 1-8103 SPENT FUEL POOL BRIDGE CRANE llNOV82 1-8105 CWI GANTRY W/ UNIT 2 1-8106 SWI GANTRY 18FEB83 1-8108 F.W. TURBINE CRANE llSEP81 1-Sill CONTAINMENT UPPER. AUXILIARY CRANE 21MAYB2 1-8112 RPV STUD JIB CRANE lOECS2 1-8113 DEMIN. FILTER HOIST 16 MAYS 3 1-830,1 CONTROL RM ANNUNICATION SYS 12DEC79 l-8302 ANNUNCI'ATOR SYSTEM RECORDERS 12MARCO l-8303 ANNUNCIATOR SYSTEM INTERCONNECTIONS 18NOVSO l-8304 ANNUNCIATOR SOLID STATE ISO. CABINET 16 IEP 8 '.- 1-8401 HEAT TRACING, NON-CLASS lE 12APRS2 1-8402 HEAT TRACING, COMMON NON-CLASS lE 25NOV81 1-6906 MET TWR & POT BLDG HVAC 070CT81 1-7001 RADIATION MONITORING LOOP 5 13DEC82 1-7002 RADIATION MONITORING LOOP 4 11JAN83 1-7003 RADIATION MONITORING LOOP 3 I?FEB83
- 1-7004 RADIATION MONITORING LOOP 2 08 MAR 83 1-7005 RADIATION MONITORING LOOP 1 15APR83 1-7006 RAD. MONITOR CONT. RM. SEISMIC RACK 24 MAR 83
7 r ACCEPTED SYSTEM DESCRIPTION DATE l-7007 RAD. MONITOR CONT. RM. 1E RACK 05APR83 1-7008 RAD. MONITOR RM-21 & PERIPHERALS 03MAY83 ; l-7301 PROTECTION & SURVEILIANCE PACKAGE 02DEC82 1-7401 MOVABLE INCORE & FLUX MAPPING PANEL 24NOV82 1-7402 MOVABLF INCORE AND FLUX MAPPING 17FEB83 1-7404 MOVABLE INCORE AND FLUX MAPPING 21FEB83 1-7601 AC DISTRIB INCLUDING MCCXB4-2 OlAUG77 1-7602 HVAC SYS INCLUDING SUPPLY & EXHAUST OlAUG77 l-7603 FIRE PROTEC & DETECTION SYSTEM OlAUG77 -
, 1-7604 POTABLE WATER PIPING, SINKS OlAUG77 1-7605 FLOOR & STORM DRAINS & SUMP '
OlAUG77 1-760,6 SEWAGE DRAINS & SUMP 01AUG77 1-7607 LIGHTING PANELS & DISTRB FROM PANEL 01AUG77 1-7701 AC DISTRIB INCLUDING MCC X54-3 OlAUG77 l 1-7702 HVAC SYS INCLUDING SUPPLY & EXHAUST 01AUG77 { - 1-7703 FLOOR & STORM DRAINS 01AUG77
- l-7704 SEWAGE FACILITIES OlAUG77 1-6102 GASEOUS WASTE PROCESSING SYSTEMRECOM 26AUG82 1-6201 MAIN TURBINE ELECTRICAL PANELS 25APR80 1-6202 TURBINE GEN LUBE & SEAL OIL SYSTEM 03SEP80 1-6203 CONTROL FLUID 27MAY81 l l-6204 MAIN TURBINE OlOCT81
( l-6205 L.P. TURB HOOD SPRY SYS 18SEP81 1-6301 GENERATOR PRIMhRY WATER 1CSEP81
- l. . _
v - 8 ACCEPTED SYSTEM DESCRIPTION DATE l-6302 GENERATOR GAS SYSTEM' OlSEP81 1-t,303 MAIN GENERATOR & AUXILIARIES 22SEP81 1-6306 ISOPHASE BUS & BUS DUCT COOLING 020CT81 1-6307 MAIN & AUX TRANSFORMERS AND GEN BRKRS llSEP81 1-6401 REACTOR PROTECTION 16NOV81 1-6501 CONTAINMENT ATMOSPHERE MONITORING 03 MAR 83 1-6601 NUCLEAR INSTRUMENTATION 270CT82 1-6602 NUCLEAR INSTRUMENTATION 29APRS3 1-6701 HYDROGEN RECOMBINER SYSTEM 18APR83 1-6801 ROD CONTROL CABINETS 270CT82 1-6802 ROD CONTROL CABLES 07JAN83 1-6803 , ROD CONTROL DIGITAL ROD INDICATION 97JAN83 1-6901 SWI HVAC 25FEB81 1-6902 SWI CHLOR BLDG HVAC 06 MAR 81-1-6903 CWI CHLRO BLDG HVAC 140CT80 1-6904 SWYD RELAY HOUSE HVAC 05SEP80 1-6905 GUARDHOUSE HVAC 11 MAR 81 1-4901 CVCS BORON THER. REGEN. & BORIC ACID 29JAN82 1-4902 BORON THER. REGEN & CORIC ACID XFER 01FEB81 1-5001 SWITCHYARD 24APR81
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1-5101 PLANT GAS SYSTEM N2~ BOTTLED GAS 2]APR81 1-5102 PLANT GAS SYSTEM H2 BOTTLED GAS llJUN81 1-5103 PLANT GAS SYSTEM, 02 SUPPLY 02JUL81 1-5104 PLANT GAS SYSTEM - OXYGEN 12JUN81 l
9 ACCEPTED SYSTEM DESCRIPTION DATE l-5105 ELECT. PENETRATION H2 PRESS SYSTEM 18FEB82 1-5106 . PLANT GAS 04DEC81 1-5201 BOP & NSSS AUX RELAY RACKS 30JAN81 1-5202 AUXILIARY RELAY RACKS 10SEP81 1-5203 AUXILIARY RELAY RACKS 06JUN83 5301 COMPUTER 06AUG80 1-5401 TURBINE GLAND STM. SYSTEM 190CT81 2-5402 TURBINE GLAND STM 22SEP81 1-5501 REACTOR COOLANT- 08APRS2 1-5601 BORON RECYCLE SYSTEM 31DEC81 1-5602 BORON RECYCLE SYSTEM 19AUG82 1-5701 SAFETY INJECTION 23JAN82 1-5601 RESIDUAL HEAT REMOVAL 29JAN82 1-6001 SOLID WASTE PROCESSING 10 MAR 85 1-6002 WASTE SOLIDIFICATION SYSTEM 06APR83 1-6003 SOLID WASTE COMPACTOR 10 MAR 83 1-6101 GASEOUS WSATE PROCESSING SYSTEM 22SEP82 1-4004 FULE HANDLING & VESSEL SERV 0200N82 1-4101 LIQUID WASi'E PROCESSING FD TANKS 200CT61 1-4102 LIQUID WASTE PROCESSING FD EVAP. 295EP82 1-4103 LIQ. WASTE PROCESSING, WAS7U HOLD UP 10NOV81 1-4104 LIQUID WASTE PROCESSING, WASTE EVAP. 180CT82 , 1-4105 L UID WASTE PROCESSING, RC DRAIN 15DEC81 1-4106 LIQUID WASTE PROCESSING, LAUNDRY TKS 27DEC82 i I
10 SYSTEM ACCEPTED DESCRIPTION DATE l-4107 LIQUID WASTE PROCESSING, R. O. SYS. 12FEB82 1-4108 LIQ. W. PROCESSING, RESIN & CHEM TKS _ 31JAN83 l-4201 FUEL BLDG HVAC 31AUG81 1-4202 SPENT FUEL POOL HX & PUMP RM COOLERS 21JUL81 1-4301 LUBE OIL PURIFICATION 08AUG80 1-4401 STEAM GENERATOR BLOWDOWN & CLEANUP 29JAN82 1-4501 CONTAINMENT PURGE 02JUL81 1-4502 CONTAINMENT VENTILATION 23JUN81 1-4503 CONTROL ROD DRIVE MECH. HVAC 11NOV82 1-4504 CONT. BLPG PRESUR ACCUM FILT. SYS 21JAN82 l-4505 NEUTRON DETECTOR WELL COOLING SYS 01NOV82 1-4506 RCS PENETRATION COOLING 25JL*N82 1-4601 CON'A AI'NMENT H2 PURGE 05JANS2 1-4701 FUEL POOL COOLING AND CLEANUP 17 MAR 82 1-4702 REFUEL CAVITY DRAINS, PURIF. & SKIM. 26JAN82 1-4801 CONTAINMENT SPRAY SYSTEM 09NOV81 J-4802 CONTAINMENT SPRAY CHEMICAL AD'DITION 02FEB82 1-3901 DEISEL GEN FUEL OIL TRANSFER 16DEC81 1-2902 DIESEL GENERATOR LUBE OIL 25NOV81 1-2903 DIESEL GENERATOR STARTING AIR 16DECS1 1-2904 DIESEL GENERATOR DIESELS 23APR82 1-3101 SAFETY CHILLED WATER SYSTEM
- 060CT81 1-3201 AUX. BLDG. VENTILATION 190CT81 1-3202 AUX. BDLG, FANS & FILTERS 13NOV81 l
t
$P 11 ACCEPTED SYSTEM DESCRIPTION DATE l-3301 CHEM FEED SYSTEM (COND) 25FEB81 1-3302 SECONDARY CHEM ADDITION (FEED) 25FEB81 1-3401 MAIN STEAM SYSTEM 31JAN83 1-3501 HFATER DRAIN 24NOV81 1-3601 SAFEGUARD BLDG - HVAC 260CT81 1-3602 MAIN STEA, &FW AREA HVAC 090CT81 1-3603 SAFEGUARD BLDG HAVAC, ELECT. AREA 16DECS1 1-3604 SAFEGUARD BUILDING HVAC, ECCS COOLER 29DEC61 1-3T01 COND STOR & TRANSFER 15SEPS0 1-3702 AUXILIARY FEEDWATER SYSTEM G2DECB1 3 1-3703 AUXILIARY FEEDWATER SYSTEM 15DECEl 1-3901 EXTRACTION STEAM 090ECS1 1-3901 DIESEI2 GENERATOR HVAC, VAFNUF-25-32 llAUGE1 1-4001 FUEL HANDLING TOOLS 02MAY83 1-4001 FUEL HANDLING TOOLS C2MAY83 1-4002 WEW FUEL ELEVATOR 28 MARS 3
' l-4002 FUEL TRANSFER SYSTEM 28 MAR 83 1-1902 CONDENSATE SYSTEM PIPING 29MAY81 1-3001 AUXILIARY STEAM 13JUL81 1-3003 AUXILIARY STEAM RETURN 13JUL82 1-3101 NON-SAFETY CHILLED WATER SYSTEM 22JUN81 1-3202 NON-SAFETY CHILLED WATER G8JUN81 1-2201 SECONDARY SAMPLING 29SEP80 1-2202 PASS 12JAN83
12 ACCEPTED SYSTEM DESCRIPTION DATE l-2203 PROCESS SAMPLE RACK AND PIPING 15DEC81 1-2301 VENTS & DRAIN TURBINE BLDG. 25AUG81 1-2302 DRAINS & SUMPS. AUX. BLDG. 160CT81 1-2302 VENTS & DRAINS AUX. BLDG. 160CT81 1-2303 VENTS & DRAINS (FUEL BLDG) 29SEP81 1-2304 VENTS & DRAINS (S.'G. BLDG) 150CT81 1-2305 VENTS & DRAINS (CONTAINMENT) 25NOV81 1-2306 D.G. SUMPS 30SEP81 1-2401 PRIMARY PLANT VENT SYSTEM 150CT81 1-2501 CONDENSATE POLISHING SYSTEM 31 MAR 81 i 1-2502 CONDENCATE POLISHING SAMPLE EQUIP. 13OCTS3 1-2601 CIRCULATION WATER PUMPS & PIPING 19APR80 1-2602 CWI CH RINATION 23CULB1 1-2701 COND VAC 31JULE: 1-2801 FEED WATER 18SEP81 ! 1-2802 STEAM GENERATOR FEEDWATER SYSTEM 13JUL82 1-2803 STEAM GEN FW SYS-MSP ALARM, ETC 290CT81 1-01DA 125/250 VDC BATTERIES 27JUL79 1-OlDB COMMON 125-250 VDC DISTRIBUTION 16AUG79 1-01DC 125/250 VDC DISTRIBUTION 02AUG79 l l-01DD TRAIN A 125 VDC SWB 290CT79 i 1-OlDE TRA'IN B 125 VDC SWBD 12NOV79 1-01DF AND COMMON TRAIN A 125 VDC 25JAN80 i 1-OlDG AND COMMON TRAIN B 125 VDC 24APR80
.3 13 ACCEPTED SYSTEM DESCRIPTION DATE l-01DH 24/28 VOLT DC 12NOV79 1-01DJ 125 VDC EMERGENCY LIGHTING 20JAN83 1-OlDK 125 VDC CLASS lE BATTERIES 14FEB83 1-01DL 'ERF COMPUTER 125 VDC SYSTEM 190CT82 1-02AA 6.SKV NORMAL SW. GR. (EXCEPT XAl) 110CT79 1-02AA 6.9KV NORMAL SWITCHGEAR, XA1 llOCT79 l-02AB 6.9KV SWGR 19JUN80 1-02AE 460V NORMAL SWITCHGEAR llOCT79 1-02AF 480V CLASS lE SUGR 19JUN80 1-02AG.1 NON CLASS lE 480V MCC's 2SJUN79 1-02AG.2 NON-CLASS 1E COMMON 480V MCC's 31 MAR 80 1-02AG.3 480V MCC XB3-2 2950V79 1-02AG.4 NON-CLASS lL COMMON 480V MCC 30JUN80 1-02AH.1 NON-CLASE lE UNIT 1 480V MCC's 300CT79 1-02AH,2 NON-CLASS lE UNIT 1 480V MCC's 02DEC79 02AH.3 480V MCC 183-3 14NOV79 1-02AH.4 NON-CLASS lE UNIT 1 480V MCCs 06 MAT 80 O
4
I 1 I l CASE EXHIBIT 856 1 ITEM 15 Information provided as requested
)
l 1 1
7 N Preoperational Test Summary Aux. Feedwater Turbine Driven Pump 1CP-PT-37-03, Revision 0 The Preoperational test of the Auxiliary Feedwater Turbine-Driven pump was started on March 3, 1983. Testings was performed from March 27 to June 9. Numerous delays were encountered resulting from equipment problems and Hot Functional Test scheduling. Testing of Control System section 7.1 through 7.4 was started prior to completing the open items of Table I (ME-1 for Turbine-Driven Pump) TPD #2. Delay of pump run-in ME-1 was due to Turbine gland and installation of break down orifice on the test line, which was resolved. During conduct of testing the following problems were found:
- 1. Flow control valve controller (1-FK-2460B). Turbine Speed
- indicator (1-SI-24525) and Pump discharge flow indicator (1-FI-2452B) failed to function properly, see TPD 902, 1087 and 1086. TDR 902 and TDR 1086 are now closed. TDR 1087 remains open pending resolution of TDR 1199. (See problem
#8).
- 2. Turbine - Driven pump was unable to produce rated flow or pressure when steam pressure was lowered to 110 psis, TDR 1142. Resolution was to accept as is, FSAR required pump to
(" operate stating no minimum criteria for pump discharge flow or pressure. The 125 psia Low Steam Pressure run was performed two times. Because the first time the Steam Pressure was 125 psig instead of 110 psig (17; psia) as required by FSAR see TDR #1118. Both TDR's are now closed.
- 3. During the first cold start of Turbine - Driven pump the-drain valve (1-LV-2383) for drain pot MS-27 failed to close, TDR 1083 problem was identified with the Drain Pot level switch being underrated for temperature it sees in operation. The switch was cleanel and during following cold i
i l starts the level switch functioned properly. remains open pending TUSl Engineering Evaluation of the TDR 1083 hM, switch.
- 4. Turbine Steam supply valve 1-HV-2452-1 & 2 leak a small (J: \
amount of steam thus preventing the cool down of steam supply piping for cold starts (Section 7.8) . TPD #13 was *g$3, written to cool down the steam piping by securing the manual *(.,p. isolation valves just up stream "of 1-HV-2452-1 &- 2. */ Resolutions of TDR 1084 is to rework the valve settings. g.3 ( Rework remains an open item to this test.
- 5. Upon starting all three Auxiliary Feed water pumps for water l
hammer test Section 7.9, the #1 Motor Driven pump trip on a low suction pressure. This was observed in prior starts of the two Motor Driven pumps and addressed by a design change
#1979. The TDCR adds a 5 see time delay on low suction pressure. Approval of change was given by DCA l
i i
A 17,007/17,386/17,387 but installation is not completed (TDR (.e #1157). TPD #21 was written to allow holding the handswitches in RUN momentarily. In doing so, the low suction pressure trip is by passed, thus si.aulating the design change conditions. The test was repeated in this manner with no problems.
- 6. During th 48 hour endurance run (Section 7.10) the following problems were observed.
, A. Pump out board thrust bearing temp exceeded the 180*F , criteria (TDR 1016). Resolution was to install a water line to the existing unused bearing water jacket. I Retested 48 hour run and the TDR was closed. B. Room temperature and relative humidity exceeded the 104*F/70% criteria, TDR 1017 and 1279. Engineering Evaluation is to use as is per GTN-65740. The TDR's were then closed.
- 7. During tesths the trip throttle valve 1-HV-2452 failed to trip shut cace the trip latch was released, TDR 1085 was written. Resolution was to bring the valve vendor on site and rework valve. Rework was completed and retest tested l sat. TDR 1085 was closed.
? 8. At the beginning of test the Turbine speed control loop (1-S-2452B) did not control properly (did not put out 3 to 15 psig as required), TDR 1001 was written. Af ter many i attempts to recalibrate it was determined that it was not possible as designed TDR 1199 was written. TPD #15 was issued to test the Turbine governor with a calibrated air supply, governor test sat. TDR 1199 remains open awaiting TUSI Engineering Evaluation.
CPSES system operating procedure SOP-304A (Auxiliary Taedwater System) was used in this test some minor problems were noted and will be submitted to TUGC0 Operations for resolution. With exception of the above items the Turbine Driven Feed Pump s tested well. The STE recommends approval of the Preoperational
~
?
3 Test ICP-PT-37-03 as conducted. MMStartup Test Engineer d -nDate - 73 .
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Page 3 of 107 2-i5-83 .3 AUXILIARY FEEDWATER TURBINE - DRIVEN PUMP
, 1.0 TEST OBJECTIVE 4
i The objective of this test procedure is to demonstrate the e capability of the steam driven Auxiliary Feedwater pump to supply feedwater to the steam generators, to maintain steam generator water inventory as required and to ensure system performance in accordance with the Final Safety Analysis Report. This test will also test Auxiliary Feedwater System (AFS) for water hammer. The
- condensate storage tank (CST) and the condensate transfer functions shall be demonstrated in 1-CP-PT-37-02. TD flow control valves 1-HV-2459, 1-HV-2460, 1-HV-2461, and 1-HV-2462 will be tested for response during a loss of instrument air in 1-CP-PT-37-01.
Note After completion of sections 7.1, 7.2, 7.3, and 7.4 Sections 7.5, 7.6.1, 7.6.2, 7.7, 7.8, 7.9 and 7.10 may be performed in any order as plant conditions determine, except that section 7.6.2 and 7.7 must
' follow section 7.5.
c' L Note (' Sections 7.5, 7.6, 7.7, 7.8, 7.9, and 7.10 will be performed during Hot Functional Test. 2.0 ACCEPTANCE CRITERIA 2.1 The control circuit for the AFS flow control valves (HV-2452-1 and HV-2452-2) and the drain pot level control valve (LV-2383) shall function in accordance with applicable design drawings. 2.2 The control circuit for the AFS flow control valves (HV-2459, HV-2460, HV-2461, and HV-2462), trip and throttle valve (HV-2452), and turbine interlocks shall function in accordance with applicable design drawings. 2.3 Satisfactory demonstration that the following AFS valves have the capability to operate for 30 minutes following a loss of instrument air Valve Description HV-2452-1 Steam inlet valve from
#1 main steam line HV-2452-2 Steam inlet valve from
.s'[ #4 main steam line iti , h',h
#
- ATTACHMENT A CP-SAP-16 Ravisien 6 s .
TEST PEFICIENCY REPORT Page 8 of 8 System Name: Ius./ J., Nefw. ev **
/ Ps.ge / of l
/ Component Tag No: /- [F- JV6o / Safety '
Non-Safety l Startup System No.:3 7- ,3 Test Instruction / Procedure No.: /c/# -N- 57-o 1 DESCRIPTION OF DEFICIENCY: /-/,e. ,2 <,r4g / ,,, //g/ 4,, /,[ ho b is h4/aAL . Component Operation M y _May Not continue until Corrective Action is complete: CORRECTIVE ACTION: [es aes IN8h Nd repu.l. se es/ e heesssx-v /--Sk- 2Y6o d' . , t, , ,- b}f 4 - yu 3,,
'*~ar vi;Ll REQUIRED RETEST: de .,- .s Ar 7, 2, 7 7,7,d 27.1 . M % r./,
>h /t/- fr 03 Initiated By: Date: ' J Engineering Evaluation of Deficiency Required: Yes MNo
. Reference Documents for Engineering Evaluation: ,
Corrective Action / Retest Approved By: 1 Date: bb Corrective Action Completed: Date: [~T #3 f )
, Retest Satisfactorily Completed: ~
Date: [- I- N
, , SystemTjstEngineer A. Scrap Verified By: A/ A Date: <t / d TUGC0 QA Startup/Tufnove'r Surveillance Supv.
Distribution: Original to Log TUSI Engineering Manager TUCCO QA Startup/ Turnover Surveillance Supervisor MSP Group
s-
' ATTACHMENT A CP-SAP-16
, Revision 6 TEST DEFICIENCY REPORT Page 8 of 8 System Name:_ Awx FuJ v 4. 4 a - TDR No. . No Component Tag No: / - F.T- Z Y 5'3 8 Page / of_ /
Safety Non-Safety g.', Startup System No.:17o3 Test Instruction / Procedure No.: / c/- AT- 7 7o3 DESCRIPTION OF DEFICIENCY: ~D u *-,% q c o** d*<.Y o f s c4 -# /T- 7 7 o J seehes 7. s- ( rio u., - 6, I /s -/ , - % lAIves ),[loh ,%Ac,k
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Initiated By: [* - / Mew ~ , i Date: Y 8'T - i Engineering Evaluatica of Deficiency Required: hs k No Reference Documents for Engineering Evaluation: rM, Corrective Action / Retest Approved By:
, Lea S. ,o tar' tup Engineer Date: h b b[
S~-/7- 83 Corrective Action Completed: Date:.f f 7 7' *
- Retest Satisfactorily Completed:
i Date: / 7 7 ( ', Scrap Verified By:
' System 'Qest Engineer
/14
/
Date: M f4 TUCCO QA Startup/ Turnover Surveillance Supv. { Distribution: Original to Log TUSI Engineering Manager ' Initiating STE TUCCO QA Startup/ Turnover Surveillance Supervisor MSP Group 4eh *
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O ATTACIDENT A CP-SAP-16 Revision 6 TEST DEFICIENCY REPORT Page ( of 8 System Name: A4x Fe<J co(fw D R 8* : bSI
. Component Tag No: / 7- Y T E N Page / of /
Safety Non-Safety Startup System No.:"J703 Test Instruction / Procedure No.: I C M7~- 37 0 3 DESCRIPTION OF DETICIENCT: 3 w i's g C a 6. 4 c.Y e f l C/-[NJ7 0 3
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CORRECTIVE ACTION: Re /)4 /c o- R.a e / as uee t Ents n'e~ . WMbN/hNhg f y REQUIRED RETEST:
.4 loe / C%
g ' 9 /200# AGhlY~ Of-9"!/ Y f I l Initiated By: No"~ N e e , ;, , ' Date: Y 70 -U Engineering Evaluation of Deficiency Required: Yes % No Reference Docun.ents for Engineering Evaluation: . < Corrective Action / Retest Approved By: W Date: Id-fl Lead Startup Engineer Corrective Actica Completed: Dete: System Test Engine r Retast Satisfactorily Completed: Date:
/ System Test Engineer
(* Scrap Verified By: Date: TUGC0 QA Scar:up/ Turnover Surveillance Supv. Distribution: Original to Log TUSI Engineering Manager Initiating'STE
- TUGCO QA Startup/ Turnover Surveillance Supervisor MSP Group
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ATTACIDiEE A CP-SAP-16
, , Revision 6 TEST DEFICIENCY REPORT Page 8 of 8
- System Name: Ax R .cA 4 >%-fe TDR No.: // /[
g] Component Tag No: I C /'- A F A "DTD- o / Safety Page / of _ l J Non-Safety Startup System No.:37o 3 Test Instruction / Procedure No.: /c/4 /T-77c,3 7-DESCRIPTION OF DEFICIENCY: _ A FTER Po form /.,9 5< c flow 7. C. I e .C 1 h. ,9 7 - n o s , i f . , -fo u J? +l.<.4- 5. ., s W fVd$$kVC $ boa h e*. "d5/ h h h l2T 'ff/h oy /l O l$$ f ef
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M7$'} P!)y i l j REQUIRED RETEST: SMJ/ E 6 /. / // w ,/ 7. 8./. S~ : o[ / -ri-J 7c 3 m Initiated By Date: 5" - 5/ - 7 3 Engineering Evaluation of Deficiency Required: Yes % No Reference Documents for Engineering Evaluation: #. , Corrective Actier/ Retest Approved By: M
/ g ). pad Sfi'f*up Engineer Date: [' I N Corrective Action Completed: /dX Mw Date:///- f.T Retest Satisfactorily Completed: Date:
(' ' System ' Test Engineer J'-/[-[7 i (' , Scrap Verified B,: A/4 l TUGC0 QA Startup/Tlknover Surveillance Supv. Date: hd Distribution: Or TUSI Engineering Menagsr MGC0 QA Startup/ Turnover Surveillance Supervisor
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ATTACHMENT A
CP-SAP-16 Revision 6 . . # e' . TEST DEFICIENCY REPORT Page 8 of 8 System Name:_ Aux Fe <cf w = 4-e r T"" "*** ! g., Page I of I e ,j Component Tag Mon c / I- A FA f TD - c) / Safety Non-Safety ~
V Startup System No.:M Test Instruction / Procedure No.: / c/-/7 03 DESCRIPTION OF DEFICIENCT: T u > e* ** % ce u ems., e.Y of Ic/ /T-77-o 3
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hYes N'o Reference Documents for Engineering Evaluation: Sc/'/.I2ff ^ Corrective Action / Retest Approved By: Date: Lead Startup Engineer Corrective Action Completed: Efte: System Test Engineer Retast Satisfactorily Completed: Date: p System Test Engineer Scrap Verified By: Date: f._.- TUGCO QA Startup/ Turnover Surveillance Supv. Distribution: Original to Log TUSI Engineering Manager
- Initiat E TUGC0 QA Startup/ Turnover Surveillance Supervisor
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, , , , _ . . . . . . - - - - - - - - - = _ . . . . -~ - ' ATIACEMENT A CP-SAP-16 Revision 6 TEST DEFTCIENCY REPORT Page 8 of 8 System Name: Auy M u O 4.> A. / w R No.: M Component Tag No: /-Il/- 2 #/ S~2 - / Page / of /
Safety Non-Safety Startup System No.:3")C3 Test Instruction / Procedure No/<! /c/8-77oS DESCRIPTION OF DEFICIENCY: ba las c o- du e-/ e -F i c#- /* 7 - 7 7 o 3 Q< *a - ? . 3 (co /) .r h, f ,t.) g__ _7 fee, jf ;,&,, , ,L e /we, J- Ht/ 'l 'l 5' 2 - / a A /-M T - / Y 'f was
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,,_,May Not continue until Correctirs Action is complete:
CORRICTIVE ACTION: N e. A.> c - 8 Vo /W eMr oa /-///- E Yff.
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fan . . . REQUIRED RETEST: /Yo A/6" f dhl)>il flll1
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Initiated By:./ [o - ~ ~ " " OM'r . Daea: */-7 6 - g 3 Engineering Evaluation of Deficiency Recuired: -lYes No Reference Documents for Engineering Evaluation: . -
- Corrective Action / Retest Approved By: M/ Date:h["b Lead $tarthp Engineer Corrective Action Completed: Date:
l System Test Engineer Ratest Satisfactorily Completed: Date: System Test Engineer . Errap Verified By: Date: l TUGCO QA Startup/ Turnover Surveillance Supv. Distribution: Original to Log TUSI Engineering Manager Initiating STE . TUCCO QA Startup/ Turnover Surveillance Supervisor
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w._ . . AMACEMENT A CP-SAP-16 Revision 6 TEST DEFICIENCY REPORT Page 8 of 8 System Name: X M ~ R No.: )M , Page / of /
- . Component Tag No: M M 88AP/71D o/ N Safety { Non-Safety I Startup System No.: UO/ Test Instruction / Procedure No.: f-68" FC T7-d $
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CORRECTIVE ACTION: iDN OAM.ll ou s 4 ries b /4.15de O C" <./%sst.2> TYT A~tt k los.? tu Dtkeons f' diua e/n&:, . r t>d m+ Jf ama.n+ L: a r .. Norach-flot n e b Y W : $ $ " + S o w N b. u =~~ A r. In - u)(1 A D h F9- ( lo f 4 sh b w s-/et -/ned a <6 ' % m/Avt J j n y g,f ~f2gf. S'$ **< REQUIRED RETEST. E'Do 6 O i. ) od WD 2 I Initiated By: M [*[ , Date: 5 /2 e' "P S Engineering Evaluation of Deficiency Required: [Yes N'o Reference Documents for Engineering Evaluation: M Corrective Action / Retest Approved By: w Date: 6-//-/f C m eetive Action Completed: c' 'J "I Date: 7M Retest Satisfactorily Complete Date: 45 5 7 j dt Engineer Scrap Verified By: Sys N tg//- Date: r1If l TUGCO QA Startup/ Turnover Survei_ lance Supv. k, Distribution: Original to Log TUSI Engineering Manager Initiatin STE GC0 QA Startup/ urnover Surveillance Supervisor MO N 1 l l
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ATTACHMENT A j',
, // ",7 CP-SAP-16
- TEST DEFICIENCY REPORT Revisica 6 System Name: Page 8 of E hX fdo) le.xh,e_
TDR No.L joM
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- Component Tag No: d#/- ###F73-d / Page_ / of /
(.,, Startup System No.: Safety 7) Non-Safety n S T ( Test Instruction /Procadure No.:
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I Initiated By: _ /drr4 //or,,n /A Date: ' (' 7 Engine > ring Evaluation of Deficiency Required: X Yes No Reference Documents for Engineering Evaluation:f#4320 l I Corrective Action / Retest Approved By: Corrective Action Completed: L A s, ,d --
/ tup Engineer Date:[-f-(( ~
Date:_[*/d- 8'7 1 Retest Satisfactorily Completed: /
-g Date: I-/C-73 system Test ngineer
~
(, , Scrap Verified By: AA Date: r8 TUGC0 QA Startup/Turnove'i S';.rve111ance Supv. i Distribution: Original to Log TUSI Engineering Manager Initiating STE MSP Group TUGC0 QA Startup/ Turnover Surveillance Supervisor
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a CP-SAP-16 Revision 6 TEST CEFICIENCY_ REPORT Pagi 8 of 8 System Name: [ [v' ea s yGM/ W
- Component Tag No:_ S 6. /2ou # Page 7 '/ Safetyi / of _ /
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Non-Safety O Startup System No.:_ 3M I Test Instruction / Procedure No.: / c/-#f- 31-o3 6 DESCRIPTION OF DEFICIENCY: _ /7/v/dexhM / Se e**
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Date: I* h~ I-Retest Satisfactorily Completed: Syst6m Test Eng'Ineer ~ f A/A Date: ' L Scrap Verified By: , SJstem Test Engineer f NA Date: s.- TUGC0 QA Startt:p/ Turnover Surveillance Supv. ~ Distributien: Original to Log TUSI Engineering Manager N TUGCO QA Startup/ Turnover Surveillance Supervisor MSP Croup O
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i ATTACICiENT A CP-SAP-16 R;vicica 6 TEST DEFICIENCY REPORT Page 8 of 8
# System Name: $4.Se
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Component Tag No: 5 (3 bo Page _ l of Y-
>.4 :st- 7 4 SafetyF Non-Safety j Startup System No.:'M C l F
Test Instruction / Procedure No.: d
/e/ -/T-? ?-07 DESCRIPTION OF DEFICIENCY: "D uc, ri c e2 54 c/c. c 4 , f s e<.f /en 7, / c o .f --
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2- u h ,e t ; a a v u lu a_.E. o.. S ec $nz S W b ll Cow &Tbl *l $"7 VO REQUIRED RETEST: Alo +1 < ~" Initiated By: _Ku I die t .k f-H .e 4 m[ /c- Ifl Date: 8-7-73 Engineering Evaluation of Deficiency Required: Yes No Reference Documents for Engineering Evaluatien: . Corrective Action / Retest Approved By: W Corrective Action Completed: / Le d S up Engineer Date: d-bk
/ Da te :[-/d - F_7 Retest Satisfactorily Completed: System /V4 Test Engineer ! h S.ystem Test Engineer Date:
( -- Scrap Verified By: ft /d Date: ,N TUCCO QA Startup/ Turnover Surveillance Supv. ___ Distribution: Original to Log TUSI Engineering Manager Initiating STE MSP Croup TUGC0 QA Startup/ Turnover Surveillance Supervisor Operations Support Engineer
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A CVty0 Cg.gaty May 19, 1983 GTN 65740 Texas Utilities Generating Company Post Office Eor.1002 hh h) Glen Rose, Tenas 76043 Attention: Mr. J. B. Gaorga Vico President / Project Gen. Manager 7 Gentlemen: TEUS UTILITIES GE::ERATING CCMPA:n* . CCPU?Q{E PEAY, STEMi ELECTRIC STATIOli
! GG PROJECT 1:0. 2322 TUGC0 TEST DEFICI5tiCY REPORT 110. 1017 REF: CPPA-30,151 The Turbins Driven Auxiliary Feedwater Pu.mp (TDAFP) is provided in conjunction with two (2) Motor Driven 7u::iliary Feedwater Pumps (MDAFP). es diverse means of supplying water to the secondary side of the Steam Generator during Plant ,
Upset of Faulted conditions. The TDAFP is not intended to operate during plent !!crncl Oparating conditions excopt for short parieds menaured in j minutea during testing. The IWAC Systs: provi.fsd for ROO:*. 374 is designed to operate only during ?lsnt 1;or:'l Caliditic:is . The six hour test perfortid by TUO00 V:3 threfore greatly in. excess of the test tito rs.!ui. red and the t3 psrature data are invalid fer ?lant ::cr::.ai Oyareting C nditions. . (> , j'a y < 3 . - 'f
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Gibbs S Hill.Inc.
'Y GTN- 65740 May 19, 1983
.1 .
During Plant Upset Conditions the HVAC System is not 4 cperating and the TDAFP will only start in the unlikely event a ' Blackout" occurs. When this occura the on-site Emergency Diesel-Ganerators will be available to power the TDAFP's within one minute. Asauming a single failure of a5mASP eS WQll as tho off-site blackcute the remaining MDAFP and the TcAFP continues to operate. Within thirty minutes the Steam Generator water demands havo decreased to the point where only one auxiliary feedukter pump is required to operate, and the TDAFP can and should be shut down. The heat loss from the TDAFP is assumed to be dis-sipated into the concrets heat sink allowing a small temperature excursion. In the case of Plant Faulted condition such as a Main Feedwater Line Rupture or a Main Steam Line Break, the TDAFP will automatically start. As scon as the core stabilitos, the water demand decreace and the TDAFP Can be shut down as describsd. The tir.s duration in this ' (~)
'- 'y
- se may, however, he 30:3What greatsr due to the time
- (, , required to.stabili:e the core and possiblo delay in operator action.
~
sased on HELB considorations please note that a co=mitment to the!NRC to limit.the.use of the TDAFP also precludes operating this pump for any long period of time.' It is therefore concluded that although the IE instrumen-tation located within Room #74 is qualified for a tempe' rature of 104*F for nor=al plant operation and 122*F for accident conditions, excursions in temperature above 104'F for a short time will not derate this instrumentation. Based on the above statements regarding the Operation of the TDAFP and the EVAC systems we see no concern with the trVAC System design for Room 174. Very truly yours, GI33S & HILL, INC. Jh T '%d
\
hA y/A I4 -[t/ RE3a"M.j Robert E. Es11ard, Jr. f'd t 1 Le'tter 0-DKG,3N-EN:ecf 7:cject Manager f c0: AAMS (35R Site) OL M. McBay (TUSI Sito) IL e p , f. p K. McDcnold (TUSI site) 1L R.D. Cal 1or (TUSI Site) IL g gg y
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' ATTACHMENT A CP-SAP-16 i
Revision 6 TEST DEFICIENCY REPORT Page 8 of 8 I 8
. System Name A4X fieeJ Wgg TDR No.: M5 Page / of /
Component Tag No: c//-AFA[TD- 01 Non-Safety "
~
- Safety y 4:
\. g Startup System No.: 370 3 Test Instruction / Procedure No.: /c/L/7~ 770'T DESCRIPTION OF DEFICIENCT: ,%w e .' '9 ccaiekucf a8 [e - / T- 7 7 - C 3
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. . .f rb f-es s u re ,, p u f e. W e u <4o.4 roo A y Component Operation @ y _May Not continue until Corrective Action is complete:
CORRECTIVE ACTION: Ne w o - k / < / e g*, 4,A /,.e M / s-l 9 O d e / c .s ,/-- " i
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[*].') f.'tr~ , . . m"* .. n%.,. I 4 REQUIRED RETEST: D [f '7'N r3 <*w a/ [. # // [/s w c = .f h ll r/e< ~ 4%truve % ll w '7 if f.I Se'd 7~fD M r Initiatad By: M4 / Me m 4 , f < Dato: _Y I 7 Engineering Evaluation of Deficiency Required: Yes No Reference Documents for Engineering Evaluation:
- Corrective Action / Retest Approved By: M Date:[~ [~ O L S tartup 8' Engineer Corrective Action Completed: Da t e : [M- P'.7 i Retest Satisfactorily Completed: Date: [- /6 - 7"?
System' est Engineer Scrap Verified By: /t Date: /,jd 4 . TUGCO QA Startup/ Turn' aver Surveillance Supv. l Distribution: Original to Log TUSI Engineering Manager Initis. ting STE TUCCO QA Startup/ Turnover Surveillance Supervisor MSP Group i
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j- . __ . _ . . - -..- - -- - ' * ~ ' " * ~ ~ ~ ~ *~~ ~ ATTACHMENT A o CP-3AP-16
-TEST DEFICIENCY REPORT Revision 6 Page 8 of 8 System Name: ; _A 4/~xY"-b.kWh Ld Q-[urp _
TDR No. : [*,[Page MC) Component Tag No:
~
2 N 2- Safety l of l
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Startup System No.:3707 Non-Safety { Test Instruction / Procedure No.: /-C[--[7-77-03 DESCRIPTION OF MFICIENCY: * /- TV-2 #5~2 A/ < > c4 / W$st C
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1 1 CASE EXHIBIT 857 i ITEM 16 Information provided as requested 9 l l
.- - .-e,
I I y,.__.,.___. . . ..-. .. _ .. _... 0FFICIAL TEST COPY INDEI TAB I - Test Summary Report TAB II - Test Procedure TAB III - Test Procedure Deviations TAB IV - Test Deficiency Reports TAB V - Supporting Documentation l l TAB VI - Chronological Test Log TAB VII - Outstanding Items (k. . O e l (
Preoperational Test Summary ( Containment Temperature Survey-
-. ICP-PT-45-06, Revision 0 STE: John H. Owen The performance of this test coveted a time span of two months due to delays incurred in the following areas. Interfacing with construction for access to the rooms containing the pump room coolers. Engineering evaluation was required prior to ratesting section 7.1 containment temperature survey.
The Containment Temperature Survey section 7.1 was tested a total of 3 , times. Upon completion of section 7.1 on 3/27/G3 it was discovered that the temperature indicators were unreliable in ambient temperature above 104'. Test Deficiency 839 was issued and section 7.1 was required to be ratested. Retest for TDR-839 completed on 4/05/83 and TDR-908 issued to identify areas that do not meet acceptance criteria. Upon completion of engineering evaluation the Containment Ventilation System was adjusted in accordance with guidelines set in CPPA-29,988. Due to Hot Functional Testing the changes in pressurizer area could not be initiated. Section 7.1 was retested on 5/18/83 and the same ( areas addressed in TDR-908 still did not meet this acceptance criteria. Test Deficiency 908 was closed and TDR-1221 issued against section 7.1 of ICP-PT-45-06. There were a total of 15 Test Procedure Deviations and 5 Test Deficiencies issued during the conduct of this test. The following test deficiencies remain open at the conclusion of this test.
- 1. Test deficiency report 1043 issued ascinst section 7.10.
This section cannot be tested until initial startup, because normal operating temperature was not reached during Hot Functional Testing for this area.
- 2. Test deficic ey reoort #1221 issued against section 7.1 Containment Survey. 7arious areas in section 7.1 did not meet their respective acceptance criteria. This area will f be tested during initial startup.
j The System Test Engineer recommends approval of the test as performed. i
\
d / W3 A l \ w %) Stirt'up Test Enginee'r"
~
Date
1CP-PT-45-06
' j, R.visita 0 y- Page 3 of 38
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CONTA7.NMENT.AND PUMP ROOM COOLERS TEMPERATURE TEST 1.0 TEST OBJECTIVE The objective of this test is to demonstrate the ability of the following ventilation systems to maintain their respective areas at or below the maximum sllowable design temperature. Containment Recirculation Cooling System Neutron Detector Well Cooling System jh N= Reactor Coolant Pipe Penetration Cooling System Main Steam and Feedwater Penetration Areas Cooling System Control Rod Drive Mechanism Ventilation System R.H.R. Pump Rooms Cooling Systems Cantrifugal Charging Pump Rooms Cooling Systems Component Cooling Water Pump Rooms Cooling Systems Positive Displacement Pump Room Cooling System Auxiliary Feedwater Pump Rooms Cooling Systems Safety Injection Pump Rooms Cooling Systems Containecat Spray Pump Rooms Cooling Systems The Containment temperature test will be performed during the Hot Functional Test Scquence while the other areas will be tested by simulating the maximum design heat load the areas are designed for. 2.0 ACCEPTANCE CRITERIA 2.1 Area ambient temperatures shall not er:eed the following at operating conditions 2.1.1 Containment Atmosphere - 120*F (7.1) ' 2.1.2 R.H.R. Pump Rooms - 122*F (7.3) 2.1.3 Component Cooling Water Dump Rooms - 122*F (7.2) 2.1.4 Centrifugal Charging Pump Rooms - 122*F (7.4) 2.1.5 Main Steam and Feedwater Penetration Areas -
-MMF (7.9,7.10) seis 7 72 O wto -roto...) .s.iy.13 2.1.6 Positive Displacement Charging Pump Rooms -
122*F (7.8) 2.1.7 Auxiliary Feedwater Pump Rooms - 122*F (7.7) 2.1.8 Containment Spray Pump Rooms - 122*F (7.5) 2.1.9 Safety Injection Pump Rooms - 122*F (7.6) em
- 1
i PC r7 O a p1 :--- 14."-PT-45-06 4/ 2 ,;-t " r; 2 .
.Revfoien 0 W d h h 2,J5 82
.. 2.2 The supply air temperature to the Reactor Vcssel
. Supports shall not exceed 90*F at operating conditions. - '
.\.
- i 2.3 Component exhaust air shall not exceed the following temperatures. (7.1) 2.3.1 Neutron Detector Wells (eight) - 135'F 2.3.2 C.R.D.M. Shroud Exhaust Ducts (two) - 163*F 2.3.3 Reactor Coolant Pipe Penetrations (eight)
Exhaust - 150*F
3.0 REFERENCES
3.1 Drawings 3.1.1 Flow Diagrams 2323-M1-300 Rev. 7 2323-M1-301 Rev. 5 2323-M1-302 Rev. 5 2323-M1-303 Rev. 4 2323-M1-307 Rev. 6 2323-M1-311 Rev. 6
, 3.1.2 I & C Diagrams
,one FOR INFDPEIION CU 3.1.3 Elementary Diagrams None 3.1.4 One-Line Diagrams None 3.1.5 Vendor Drawings None 3.2 Vendor Manuals Nuclear Axivane Fan Operators Handbook, Joy Manufacturing Company, CP-0092.1-001 3.3 Documents 3.3.1 FSAR Volume V Section 3.11B and 3.11N,
" Environmental Design of Mechanical and Electrical Equipments."
l l
, . . , - - , - . ~ , - --- - - - - - . - . - - . -- -,-n -,--- o -
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, , . 6.5.1 Non-Safety Ventilation Chilled Water System - c g. , y add[ M uN . ~5T2 8
\ Name/Date-6.5.2 Safety Chilled Water System 7Acv I t *il'.2 Name/Date 6.5.3 Containment Ventilation System (7.1) gev44 , _-, ,, g
.r- d m 6.5.3.1 Containment Recirculation Cooling System M - ,l-3 M 3 6.5.3.2 CRDM Ventilation System O"Y, f- 4-W _M;, N. . .Ehb gas,,s) ND9/Dateu .s .'t.3 6.5.3.3 R.C. Pipe Penetration Cooling System .ere[#W Y FT I s .
6.5.3.4 Neutron Detector Well Cooling System
,90 *v"N
[ Name/Date 6.5.4 Auxiliary Building Ventilation System 6.5.4.1 Centrifugal Charging Pump Rooms Cooling System (7.4) [Mg 3-% TJ Name/Date 6.5.4.2 CCW Pump Rooms Cooling System (7.2) 7/Ls.v- *$ T 'TJ Name/Date 6.5.4.3 Posith e Displacement Charging Pump Room CoolL,;:, System (7.8) M doe ~ S- T3 Name/Date 6.5.5 Safeguard Building Ventilation System
, 6.5.5.1 RER Pump Rooms Cooling System (7.3) ~[ /) r,v 9 - 7 T ,T. 's Nene/Date 6.5.5.2 Containment Spray Pump Rooms Cooling System (7.5)
IL Name/Date V T T3 6.5.5.3 Safety Injection Pump Rooms Cooling System (7.6) J4).v .y 's T 13 Name/Date 6.5.5.4 Motor Driven Auxiliary Feedwater Pump Rooms Cooler Test (7.7) EbuW 'a 4 -Y3 Name/Date 6.5.6 Main Steam and Feedwater Penetration Areas l Ventilatson System (7.9, 7.10) ,~.,/ d e~ g .47,3 Name/Date ! 6.6 The following pre-operational test procedures have been ! completed and the test results reviewed in accordance with Startup Administrative Procedure CP-SAP-11. (Section 7.1) 6.6.1 PT-45-02, Containment Recirculation Cooling g System 4. V 147'3 Name/Date ! 6.6.2 PT-45-03 CRDM Ventilation System *[dr.v 3 4 5 - jd' l Name/Date 6.6.3 PT-45-04, Pre Access Filtering and RCS Pipe , i Penetration Cooling System ,( 89= 3 IJ T3 ame/Date l l 6.6.4 PT-45-05, Neutron Detector Well Cooling System 7 4 .s. *
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Name/Date i 5 iYi fl
1CP-PT-45-06 m- r ~~' 7 'I Revision O
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Page 8 of 38 12-15-82
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7.0 PROCEDURE
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Note The following major procedure steps (7.1, 7.2, ..., 7.10) may be performed in any sequence as deemed necessary by the responsible STE and when plant conditions permit. 7.1 Containment Temperature Survey - This section shall p 7"'O . R demonstrate the ability of the Containment Ventila- _pT(39 tion Cooling System to maintain temperatures at or below design temperatures at operating conditions. gg./ d- T 73 4 <> n J[ +, 7.1.1 Verify the applicable prerequisites of paragraph ] -]
- 6.0 are complete. s. vu,w ,w e Name/Date 7.1.2 Verify Hot Functional Testing has commenced ant N g 7 1 . , bfN-plant conditions are as specified in reference N'EL*A* * ' 5 %^ * ' ""
3.3.9.1. and primary temperature is 557*F an
- i primary pressure is 2235 psig. ,,
*?""
g)line/D'steJ-7.1.3 Verify the following Contsinment Ventilation .g # Cooling Systems are in normal operation in M* N C g accordance with S0y-pl. g';fdo *s, .v) M3 g , g ,
's" "I # $ j.fs 7.'1.3.1 Containment Recirculation Cooling System M a ,} 3 I N Name/Date .
i U , 7 .m 7.1.3.2 CRDM Ventilation System N.'[.>d f, h ,' a-kI M k.N-W2 7.1.3.3 R.C. Pipe Penetration Cooling Syste M .f ,ame/Date/ ; 20 *$
- Name/Date
.h.).g 7.1.3.4 Neutron Detector Well Cooling System .i .cta.-7 ^_-.) i 4 4 Name/Date
! _,. m _7,.1.4 Monite: C:nteint:;t sv:r ;;; t:;;;reture ,.g.g-l " " ' 1 ".e _ </* i=dierter 1-T!-5':00/'. nd.:::::d ::a41ngs on- , _ ,n y., 6
"-- - 1 :: l' -i ,,%.,, 3"~~
l >X:W = D M'/ 5 a* nut:~~h' Oint: ve@'e O S~-
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pagejogge l 7.1.5 When 4 consecutive readings are within 2 3*F W"*'4 d v d'lMS , of each other, record the data on Data Sheet 2. 71,./ 3 4,' 'o$ l Name/Date 7.1.6 For the following ventilation systems, start the I standby fan and stop one of the running fans. 7.1.6.1 Containment Ventilation System F"h.,r . ~/ -~ ~ r wd Name 7.1.6.2 CRDM Ventilation System $$U W 5 ( v D }Date 2 % 7.1.6.3 Neutron Detector Well Ventilation T94ystem s! N y,pame/p"aee 7 ,,, m&f s%
~
Name/Date 7.1.6.4 R.C. Pipe Penetration Cooling System -@-%3 (Loop 2 and 3) Y % iii N ' _- + M -2 ' 7- ^ 2'-j Name/Date
=
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"~ 1CP-PT-65-06
-C Revision 0
-- 9
, 'h.' Page 9 of 38 l
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12-15-82
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7.1*I615f R.C. Pipe Penetration Cooling Systemv Dy y ,, ,,, o _ @ f k.-
- ".'s (Loop 1 and 4)
. 44T,bd 4 d7 i3-Name/Date 7.1.' Y. ;it:r C:;;;i;;;;: :::r:;;: ::;;;rature, -, " Q' g_ n . . . , _ v _ u nn n. . . . . u ng ,_,o, C ,q h o
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b *ame/DacI,.4' O 7.1.8 " Whenfourconsecutivereadingsarewithin23*Fy#[/!e-["iJ)IJ of each other, record the data on Data Sheet 2.Nt % Name/Date 7.2 Component Cooling Water Pump Rooms Cooler Test This section shall demonstrate the ability of the Component Cooling Water Pump Room coolers to maintain temperature at or below design temperatures at maximum heat load. 7.2.1 Verify the applicable prereo,uisites of paragraph 6.0 are complete. $cy 4 - rs - 53
' Name/Date 7.2.2 Verify the CCW Pump Room Cooling System is lined up for operation in accordance with SOP-806A. M)o tv -- 4 -2 f-f3 "Name/Date 7.2.3 Verify that there are no heat sources in CCW -
Pump Room - Train A. Wo~ - f+ 9,3
~
VName/Date
.. 7.2.4. Start cooler fan #09 by turning hand-switch 1-HS-5800A to START. D rv- _ 4 S3 UName/Date 7.2.5 Install a space heater that is capable of producing 116000 BTU /ER min. in the room. % rw 4 Zl- %3
*Name/Date
- CAUTION Place the space heater in a location where the direct heat will not cause equip-ment damage.
7.2.6 Close the room air supply and exhaust dampers using handswitch X-HS-5758. YCrw 4-Pr-g3 Qiame/Date 7.2.7 Piacethetemperatureprobeof4.1intheroom attached to the DVM of 4.2 outside the room. NO,vv 4 D
*Name/Date 7.1.d Shut the room doors. %~- h -2 8- SJ VName/Date-7.2.9 Energize the space heater and adjust it so that it produces 116000 BTU /HR (min). M ~~~~ 4 5'3 J NamelDate 7.2.10 Record the pump room temperature readings on Data Sheet 3 at 5 minute intervals. YCW 4 O ' h, JName/Date FO R liFC R u ailD a H Y
4
;j-0FFICIAL TEST COPY e
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"NONE"
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ATTACEMENT A CP-SAP-16 9' EST RE ae8 f8
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Systea Name:
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'{ Page \ of .2, Component Tag No:_ 7 8 //d) / --
Id /gdr[ Safety $' Non-Safety Startup System No.dk Test Instruction / Procedure No.:/- C.9-62M* d I DESCRIPTION OF DEFICIENCT: /A A=- Aff/);/p / M 7 p-gy g' MMO JY h45#O$n n #-- X.Ag-0o / /3 Y / OA-hs -Adf. pgf App & A A 8 M f>Cs'.Ar N AJ/A YW# 19fArf;-$ TdMA - N *- hD6%T _ Component Operation %_May _May Not continue until Corrective Action is complete: CORRECTIVE ACTION: T /:s & ) h,/ oh / 6f2M <,ld~ <::/ f TD kA h f [./.E) E O ' p - , FOR IU:MN .: U REQUIRED RETEST: 3",d-F 7, / [ /. (([,/ - M6". <')[ t s _ m (b Initiated By i _
'3 - f [ - b_
Engineering Evaluation of Deficiency Required: Yes b l No ' 2 Reference Documents for Engineering Evaluation:_ e
- Corrective Action / Retest App ve B: Date:.I"2.[['f La Corrective Action Complete m e gi s.
E %)neer " Date: 41 -f -d Ratest Satisfactorily Complete Date: M Sjhk(em*T'est Engineer
. Scrap Verified By: Date:
l TUGC0 QA Startup/ Turnover Surveillance Supv. Distribution: Original to Log TUSI Engineering Manager
'. Initiating STE TUGC0 QA Startup/ Turnover Surveillance Supervisor
. MSP Group SAP-16-1
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' DORIC OWNER'S MANUAL I
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SERIES 400A DIGITAL TRENDICATORS ~
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DOAlc SCENTWIC DNtsiON EMER$0N ELECT Ric CO. 3843 RurrsN acAD
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20* < 32*F ' ~~
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30* < 32* F < 50* l
! Pr.100 * *n la +v end .: io 20* < 32*F 4 60*
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-v isads. Fe Con 40* < 32' F < 30* 'D in +V and .l lum. Cu Con 2 -V leads. ,, , .
30* < 32* F < 60* , continuou 230 wag r j . E l ! Stability with temperature: I "J - ,; Cold junction:(TC ranges onlyl0,025 degrees / degree from to to*;4C(Cl505:s104*Fi for base en t J *' types; O C5 degrees /destee f or noble metsas.sgg- ,i 4 Instrument zero: ! t uV/*C for Models 400A and 402A except 2 pVfC on ij range j' 0.5 mV/*C for Models 410A and 412A escept 1.5vu fC on is reap - instrument span: 3 gg,n, ,, y g 0.01% ROG/*C for Models 400A and 402A escept 0.02% ROG/*C on 1 .
.,l.'.,
f range 0.005% ROG/*C for Models 410A fnd 412A escept 0.015% ROGfC on .
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'T g 13 range Stability with time: , 4 *.
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gV - Instrument zero: Q " f No measurable teto drift Instrument span: 5'.r
' ? ! , . ,
0.1% of ROGlyr for transmitter and voltage ranges;less than 1*/yr for TC, r 'lr . ,; RTD. and TH ranges. @ *.c ' f.*, Repeatability: .' .; . . f .' - - 21 digit except on listed 410A. 412A. 415A ranys: *s~ s2 pV on K1, CU and TH ranges. ::< - 20.2*C or F on R. S. and S ranges, so.2* F below -200* F on T range. Ch"i* 1; . .. ', .
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' ATTACHMENT A ..
CP-SAP-16 Revision 6
- TEST DEFICIENCY REPORT Page 8 of 8 f .
Systen Name: b $ d h .v/) WD a) ***
-(~ Component Tag No:_
- Page / of 8 Safet
- Non-Safety F"""9 "Startup System No.:YI 81 ,
\., I \
Test Instruction / Procedure No.: /- 88-//7M- dd DESCRIPTION OF DEFICIENCY: TA/M N/oN/ AS>r4 /2 5 %A MY A).4Es
~7X48' A &~J"' WAF WA.8
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,_May Not continue until Corrective Action is complete:
COPAECTIVE ACTION: Se 4. M M .tf ff P
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I NN MErW1.97M natq U-REQUIRE RETEST: - - umm u.s useg,g - Initiated By: /E Date: -d- 3 Engineering Evaluation of Deficiency Required: Yes l No Reference Documents, for Engineeriss Evaluation:/ fu- J^ BJ2-1Q *
,d [ L 7 'f , p y.g Corrective Action / Retest Approved By:
Date: Corrective Action Completed: Lead Scartup. Engineer i System Test Engineer Date: f Retest Satisfactorily Completed: (, ( System Test Engineer ~ Date: Scrap 7erified By: Date: TUCCO QA Startup/ Turnover Surveillance Supv. E f Distribution: Original.to Log . . . . .. . , ' :r~~r w ke
'"--) $'hh TUSI Engineering Manager . . . . . .
Initiating STE
- TUCCO QA Startup/ Turnover h ~a411**--
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(' (. . DATA SHEET 2 (Sheet 1 of 3)
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_ CONTAINMENT TEMPERATURE SURVEY g2 p[j
.' PARAMETER
~
ACCEPTANC INDICATOR 7.1.5 7.1.8 CRITERIA s j
- Centainment Fans CRDM 1Ans circleRunninfFan's
. M 3G M 4 .
NA . Circle Running Facs ~ ~1 b 2 NA lieutron Detector Well Fans Circle Running Fans h/o 'T ! g u.g AN R.C. Pipe Penetration Fans Circle Running Fans 163@ d 2@4 NA
. u RCS Temnerature T
m g g g ww.4.w.n . - Loop 1 Hot Lc3 1 ! ! ' !;.4
%Efn'YWs1 -Two %w h NA Loop 1 Cold Lag -
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NA . Loop 2 Roc Les . _
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= 84 wo w.g !! t 2. 0 NA Loop 3 Hot Leg
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*'A~OM t =rw.Y'. w4.n2 2 NA Loop 4 Hot Leg zgs h w% :w.4% TI 21
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NA _RCS Penetration Temp '
- Loop 1 Hot Leg 5 ' T # - # d M *
- I.*6.rt'* / [ /[O 150*F i
Loop i .'old LegSEK T- M N M N /[O __/8 '1 0*F Loop 2 Hot Leg utt'i34w3W444b _ /O // 150*y . Loop 2 Cold Leg sto;@dWD y. 4.@.,/ rt- M
/) M ,J50*g Loop 3 Hot Leg s <T3.tw&:We 4 +-D. Art- /
8 30*g,g Loop 3 Cold Leg Esr!."T4.b%S"'*M NN -
, o 150*F I Loop 4 Hot Leg ST E T M ~M M 8~
M /)1 150% Loop 4 Cold Leg % E T. D w.s.DO .g3 M 120
- -- 150*F g
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SK/IWD*T Revision 0 T.#.s.73 f2N3 2 DATA SHEET 2 (Sheet 2 of 3) g CONTAINAZNT TEMPERATMF S R VEY
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PARAMETER INDICATOR ACCEPTANC' 7.1.5 7.1.8 CRITERIA Loop #2 Cold Leg " "
'N Y-t 90*F Loop #3 Rot Leg mg.g9\wwo w w 1% ~
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,t 90*F
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90*F
, Detector Well Coolers
, fop Temp
#10 Temp
- 1-T1-5438 '
j f 98 # NA C 1-TI-5443 /88 -
/dd 0 NA
_ Detector Wells 1-TR-5407/ Point 1-TE-5445 .e-I .m .- 1 t,'/4/"Sh./4dSA # 135'T 1-TE-5446 -- . -4 2 _ //I O _ //go ( 1-TE-5447 3
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. . . - _ 135'T 5 // T' //[# 135'F 1-TE-5450 6 /j d~ / 26 135'F 1-TF-5451 7
s /) f C /f/ '135'T 1-TE-5452 - 8 -
/ C 135'T CRDM Shroud ~ genM* O 1-TI-5454 _/jd'~# _ Md~
- CRDM Shroud ' -it98?
Ta t'T:7b =6 1-TI-5455 /$6 _/~fd * +298?- CRDM Fan #01 1-TR-5407/Pt. 13 /OM /f /[ # NA CRDM Fan 802 1-TR-5407/Pt. 14 /.3d /d k# NA Containmenc Average Temp. 1-TI-5400/4 h# .[( 120'y Containment Fans 1-TR-5407/Pt. *
#01 Outlet 9
NA j f02 Outlec
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JJ . 6:3 4 ** - + - T (. ,3 2 K. DATA SHEET 2 (Sheet 3 of 3) CONTAINMENT TEMPERATURE SURVET o > PARAMETER - ACCEPTANCI INDICATOR 7.1.5 7.1.8 CRITERIA
#04 Outlet 12 Y[ _ -Y90 yA PIR Temperature
- 1-TI-454 ..'~
# d"'.7
- S T J' NA hssw.'r.?.%
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ATTACHMENT A CP-SAP-16 R;vicien 6
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c, o CASE EXHIBIT 858 ITEM 18 Information provided as requested
< s ICP-PT-55-02 INDEX Volume I Tab I - Test Summary Report Tab II - Test Procedure Tab III- Test Procedure Deviations Tab IV - Test Deficiency Reports Tab V - Supporting Documentation (RCP vibration data)
Tab VI - Chronological Test Log Tab VII- Outstanding Items Volume II Tab I - Data Sheet 2, RCS Chemistry Tab II - Data Sheet 2, Pressurizer Chemistry ( Volume III Tab I - Data Sheet 2, S/G #1 Chemistry Tab II - Date Sheet 2, S/G #? Chemistry Tab III- Data Sheet 2, S/G #3 Chemistry Tab IV - Data Sheet 2, S/G #4 Chemistry Volume IV Tab I - Data Sheet 3, RCS Pressure / Temperature during HFT FOR I!!FORi!ATIDN DJ.Y
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DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
G s Preoperational Test Summary Hot Functional Test Sequence
. \- ICP-PT-55-02, Revision 2 STE: Dan Parker This test successfully demonstrated the ability of plant systems to heatup the Reactor Coolant System to its normal operating temperature and pressure (557f and 2235 psig), to maintain those steady-state conditions, and to cool the plant down to ambient conditions. The ability of some safety-related systems (in particular, the Residual Heat Removal and Safety Injection Systems) to perform their safety functions was also demonstrated.
The Turbine Generator was brought to its rated speed during nine turbine rolls, which provided an adequate checkout of the mechanical and electrical systems associated with electrical generation. In addition, Operations personnel received valuable training while running the plant systems and their operational procedures were trial-tested under actual conditions, providing useful corrections or refinements to those procedures. HFT OVERVIEW Hot Functional Testing (HFT) encompassed a thirteen week period from February 24 to May 27, 1983. As shown on Figure 1, the heatup phase lasted from February 24 (filling of the Reactor Coolant System) to attainment of hot standby conditions on March
- 26. Several problems were encountered which delayed or slowed down this phase of the sequence. After filling and pressurizing the RCS, the primary side drain valve IRC-8079D on steam generator #4 developed a body-to-bonnet leak which required depressurization and draining of the RCS. Repair of the valve required a two day delay in the schedule (See TDR 679). As various testing plateaus were reached (250F, 350F, and 450F), the thermal expansion program of PT-55-11 required significant time t
to measure, evaluate, and re-measure the large number of pipe l supperts involved in the program _(over 4000 supports were l involved). The instrument calibration program, as expected. caused long delays in heating up the plant. This delay was expected since many instrumentation loop calibration procedures were not available prior to HFT. Therefore plant evolutions were held up until the required instruments were calibrated. At the 450F plateau it was determined that RcP #3 tie rod TR-3 vas l binding on its wall bracket and the tie rod was required to be removed (See TDR-846) . This necessitated plant cooldown to 325F to free the tie rod for removal and subsequent heatup to restore plant conditions. Approximately two days were devoted to this evolution. The total heatup phase consisted of 31 days. p
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pM DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
< s ,, The hot standby phase of HFT lasted from March 26 to May 22, for a total of 58 days. This phase of the program contained the bulk of the HFT testing while systems were running under normal operating conditions. The testing generally proceeded in an expeditious manner, although there were several delays for equipment repairs, ratests, or procedure preparation. As shown on Figure 1, there were two cooldowns during the hot standby phase. The first, on April 13, was required in order to remove tie rods from RCP's 1,2, and 4 which were binding on their wall brackets. Cccidown to 275F was was made in order to free the tie rods, causing a three day delay (See TDR-971). The second l cooldown, which lasted from May 2 to May 8, was required in order
- to make several repairs. The letdown orifices TBX-CSORLB-01 and 02 which failed their acceptance criteria during PT-49-02 (by providing too much flow) were replaced during this period.
, Charging valves 1-8146 and 1-8147, which had developed !. body-to-bonnet leaks, were scheduled for repair, but since upstream check valves -leaked through, only the bonnets were torqued and the valves will be repaired after HFT. Also, during the cooldown, 1-8141D (RCP #4 seal return isolation) was repaired due to binding of valve internals. Since RCP's draw higher current at lower RCS temperatures, the cooldown period had
- optimum conditions for the transformer load test PT-02-13 which was satisfactorily completed. Overall, this cooldown delayed the schedule by seven days, but completion of PT-02-13 and several l other tests made the cooldown a beneficial evolution. At the end
- of the hot standby phase there were additional delays due to BTRS chiller problems which prevented speedy completion of the RCS boration and dilution tests of PT-49-05.
The final plant cooldown, a five day evolution, occurred in a most expeditious manner. Figure 1 displays the cooldown as two separate cooldowns around 325F. This was done in order to checkout each train of the RHR system and its ability to cooldown the plant.
SUMMARY
OF HFT TESTS The various preoperational and acceptance tests which were performed during HFT are listed below. If specific details on test performance are desired, the test summary for that particular test should be reviewed. l " % niiu,j y;jzy i *
- 1. . -
DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
o s
.. Procedure Title PT-02-12 Bus voltage and Load Survey FT-02-13 Power Transformer Load Test PT-02-14 480V Switchgear Transformer Load Test PT-22-01 Process Sampling System AT-22-02 Secondary Sampling PT-22-03 Post Accident Sampling System AT-28-01 Feedwater System Test PT-34-01 Main Steam Isolation Valves PT-34-02 Steam Generator Safety and Relief Valves AT-34-03 Steam Dump l
System Operation PT-34-05 Steam Generator Narrow [ Range Level Verification Auxiliary Feedwater I PT-37-03 Turbine-Driven Pump
] tl
{ (ff ! AT-44-01 S/G Blowdown Cleanup System Hot Functional , Test PT-45-06 Containment and Pump Room Cooler Temperature Test PT-49-02 Sealvater and Letdown Performance PT-49-05 Boron Thermal ! Regeneration System PT-55-03 Pressurizer Safety and Relief Valves - l I
*#,'g a DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
+ ,. . . . _ . - - . - . - .- - --
a s PT-55-05 Pressurizer Level Control PT-55-06 Pressurizer Spr.ty and Heaters PT 55-09 Reactor Coolant Pump Test PT-55-10 Pressurizer Pressure Control System PT-55-11 Thermal Expansion PT-57-09 Check Valves and not Functional Safety Injection PT-58-02 Residual Heat Removal at Hot Functional AT-62-05 Turbine Roll PT-74-02 Incore Thermocouple and RTD Cross
- Calibration I, i ,
d PT-91-01 Loose Parts Monitoring i l l l
~~
DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
d 8 REACTOR COOLANT PUMP SCMMARY React!>r Coolanc Pumps operated in a. fairly satisfactory manner during HFT, considering that is was the first time they have been run for long periods. Several problems concerning seal performance were noted during HFT. The Number 2 seals are to be modified af ter HFT, which should limit related problems in the future. Four Test Deficiency Reports (TDR's) were prepared to 0 document RCP seal discrepancies during testing or operation:
- 1. TDR-946 to PT-49-02 documents high flow rates f ro 2 all RCP No. 2 seal leakoffs (TDR is open).
- 2. TDR-lll4 to PT-55-09 documents seal flow problems on all RCP's No. I and No. 2 seal leakoff flowrates and RCP #1 and
#2 No. 3 seal flowrates (TDR is open).
- 3. TDR-894 to PT-55-02 documented RCP #3 seal problems which ,
later were resolved when raising RCS pressure caused the seal to " seat". (TDR is closed).
- 4. TDR-1200 documents RCP #3 No. 3 seal leakage to atmosphere (TDR is opsn, corrective action to be performed on TDR-ll14).
Another problem of RCP breaker trips was resolved on TDR's 954 and 955 by resetting the 50 M1-51 overcurrent relays. These TDR's have been closed. RCP operational data is as follows: {j l RCP #1 RCP #2 RCP #3 RCP #4 Run Time 1938 hours 1791 hours 1678 hours 1868 hours Number of Starts 26 35 22 37 During HFT, at least 240 hours of RCS full flow were required in order to put reactor vessel internals through one million cycles of vim ation for post-HFT inspection of internals. In actuality, the RCS underwent 1486 hours of full flow, of which 991 hours occured at temperatures above 515F and 495 hours below 515F (k'es tinghouse requires at least half of the 240 hours to be at temperatures above 515F). Reactor Coolant Pump vibration was monitored at various stages of the plant. heatup for all RCP's u::ing hand-held vibration equipment. None of the RCP's exhibited vibration problems (see data at Tab V) . After their initial runs, RCP's 1, 2 and 4 were balanced. The permanently installed Bentley-Nevada vibration equipment did not display any vibration readings that were out of specification, although a few spurious alarms were noted. Og'g 3 DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW l
e = l PIPING VIBRATION (-" During the RCS heatup the RCS and Main Steam piping systems were monitored for piping vibration. The RCS piping was also I monitored during the cooldown. No piping vibration prgblems were
-noted. Other preoperational tests monitored piping vibration on ,
the system affected (e.g. PT-49-02 monitored CVCS systw piping vibration during HFT). See those specific procedures for details. HFT CHEMISTRY The Reactor Coolant System chemistry during HFT was outstanding. The only problems noted were high silica readings from March 6 to March 14. The silica was removed utilizing the CVCS mixed bed demineralizer. Lithium concentration periodically di? ped below
.1.0 ppm but lithium hydroxide was added as necessary (plant pH l remained in specification). RCS chemistry problems are noted on TDR-1277, which is closed.
The Steam Generator chemistry started out in poor shape, as was expected for the first heatup of the carbon steel secondary side. However the steam generators were gradually cleaned up using the blowdown and condensate polishing systems and at the end of HFT the steam geaerator chemistry was fairly consistent. See TDR-1276, which is closed. RCS chemistry results are documented in Volume II of this procedure and steam gene ator chemistry in Volume Ill. TEST PROCEDURE DEVIATIONS Fif ty-three TPD's were written f or this procedure. Twenty-eight TPD's incorporated administrative changes to allow greater flexibility in testing, to add or delete tests, or to establish conditions for testing. Nine TPD's were written to make technical changes to the procedure, such as changing setpoints or heatup rates. Six TPD's were written for guidance to Operations 1 personnel on running certain systems or temporary systems during l HFT. Finally, ten TPD's were entered to correct typographical errors. , l I a bl DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
o . TEST DEFICIENCY REPORTS i Eight TDR's were prepared to document problems directly relating to PT-55-02 (See the various system procedures for TDR's which discuss failures during individual preoperational .or acceptance tests): TDR Component Problem Status 679 1RC-8079D- Leaking valve Closed 894 RCP #3 No. I seal leakoff Closed excessive flow 954 RCP #4 Breaker tripped Closed 955 RCP #2 Breaker tripped Closed 1270 AFW indication Indicator problems Open at Remote Shutdown Panel 1276 S/G #1,2,3 & 4 Out of specification Closed chemistry analyses 1277 RCS Out of specification Closed . chemistry analyses 1323 Steam Generators Maximum RCS to S/G Open differer.tial pressure exceeded 1909 N/A Discrepancies in Closed chronological log The System Test Engineer recommends approval of the test as performed. l
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e
- m 1CP-PT-55-02 hi4 .it ersc=mheen
?
p1, g hr Revision 2 0 4 b.: d Eas $bz t i 1 Page 3 of 59 02-07-83 HOT FUNCTIONAL TEST SEQUENCE
,, 1.0 TEST OBJECTIVE To demonstrate the satisfactory performance of systems and components during Reactor Coolant System heatup, at normal operating pressure and temperature, and during Reactor Coolant System cooldown.
2.0 ACCEPTANCE CRITERIA 2.1 The systems and components checked during Hot Functional Testing function in accordance with design specificaticas and applicable FSAR requirements. Applicable Technical Specification requirements are satisfied. 2.2 See individual preoperational tests for the specific acceptance criteria of those procedures (from Reference 3.3.7). 2.3 The following modes o* eperation shall be observed and/or measured (as applicable) and determined to be acceptable per the Preoperational Vibration Test document (Reference 3.3.6;. Mode of Operation Type of Vibration
- 1. Reactor coolant Steady state and system heatup transient
- 2. Reactor coolant Steady state and system cooldown transient
- 3. Main steam system Steady state and
, during warmup transient 1
3.0 REFERENCES
3.1 Drawings 3.1.1 Flow Diagrams 3.1.1.1 2323-M1-0202, Main Steam Rcheat and Steam Dump, Revision 11 3.1.1.2 2323-M1-0202-1 Main Sterm Reheat and Seam Dump, Revision 7 3.1.1.3 2323-M1-0203-1, Steam Generator Feedwater System, Revision 2 , , , ,
]
3.1.1.4 2323-M1-0204. Condensate System, Revision 7 l
. w. ,
DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
i ATTACHMENT A CP-SAP-12 Revision 1 TEST INSTRUCTION / PROCEDURE DEVIATION Page 7 of 7 0FFICIAL TEST 00PY :: . 1 o, 1 Test Instruction / Procedure No.: PT-55-02 Re v. : 2 - Test Instruction / Procedure
Title:
HFT Sequence Rev. 2 k Affected Equipment: Post Accident Sampling System Deviation
Description:
- 1) on nace 8 delete step 3.3.7.6 21 on nace 29 delete step 7.2.8 m or- nacej8 delete sten 7.3.23 10R W~.
- m e.ay,ygy, N4 Reason for Deviation: The PASS system preocerational test PT-22-03 is gn<ng en k, vourieten and will be performed when the equipment for analyzing PASS samples arrives en site.
l Change to Intent of Test: y YES NO Procedure Revision Required: N/A YES N/A NO (Applicable to Pre-Req Tests Only) Initiated By: c: M Date: 8////'83 i Concurrence: SHIFT SUPERVISOR: M Date: " i t Review / Approval: STE/ TEST 71 RECTOR: , /4 f.( h Date: 8-//-[I LEAD STAP. TUP ENGINEER: Date: 7-//-/_f A JOINT TEST GROUP (JTC) MANAGER, NUCLEAR OPERATIONS: ' [ m3/ . j// ff Date: ,2- //- /3 i Station Operations Review Come ttee: g/ MANAGER, PLANT OPERATIONS: /V. . Da:c: N/ l... DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
CP-SAP-12 ATTACHMENT A Revision 2 Page 6 of 6 TEST INSTRUCTION / PROCEDURE DEVIATION Test Instr./ Proc. No.: ICP-PT-55-02 Rev.: 2 TPD No.: 46 Page 1 of I Deviation
Description:
- 1. Delete step 7.3.62 (hydrogen addition to the RCS) . {PA66 f0R IMtc~,, .
ReasonforDeviaticN
- 1. Hydrogen analysis equipment not ready to suonort hydrocen addition.
I Change to Intent of Test: X YES NO Initiated By: 7/// 4 > Date: MM/IVO y-STE/ TEST DIRECTOR APPROVAL: MM7 #4; Date: /9/M//d I SHIFT SUPERVISOR CONCURRENCE: ~ e ._ Date: /4 0, II l LEAD STARTUP ENGINEER / LEVEL IV: ,% [' Date: / d- n. I,3
'J l... '
DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
. e
-n mW (I4; D ' 0.Y 5-2pF ('
- g. . . .
n I k 4 3 ,61 y
',7'. i'
? ..-)c. I[I W QAZ3KeHMENT A CP-SAP-12
.g'2y Revision 2 O Page 6 of 6 TEST INSTRUCTION / PROCEDURE DEVIATION Test Instr./ Proc. No.: 1-CP-PT-55-02 Rev.: 2 TPD No.: 50 Page 1 of 1 Deviation
Description:
Delete the following steps: .
- 1) step 7.2.39 on page 32,
- 2) step 7.2.61 on page 35,
- 3) step 7.4.16.1 on page 48A.
1 Reason for Deviation: Components exhibited improper equipment preformance. Refer to TDR 1114. < \ rnn 11 tim...1T UV Change to Intent of Test: X YES g;.M3 -tm Initiated By: Date: 26 Mav, 1983 l I STE/ TEST DIRECTOR APPROVAL: yYj[ Date:[4% d6/993 l SHIFT SUPERVISOR CONCURRENCE: h%, page $ , "76 -f,} /\ LEAD STARTUP ENGINEER / LEVEL IV, ) Date:
' ' S7k-83
\...., l... l... DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
. n CP-SAP-12 Revision 2 0 101 NS 0P9 d/ ROCEDURE DEVIATION Test Instr./ Proc. No.: ICP-PT-55-02 Rev.: 2 TPD No.: 53 Page 1 of 1 Deviation
Description:
- 4. On page 8, add step 3.3.7.6 PT-22-03. Post Accident Samoline System.
Revision 1.
- 2. On page 29, add step 7.2.8 as follows:
7.2.8 Perform PASS sampling of RHR system in accordance with PT-22-03 Rev. 1 Section 7.15. Lineup RHR system in accordance with SOP-102A to support the test. n, pego in esa fn11nue. 1 e.e7
- 7_77 ne 7.1.71 Perfntm PA99 nerfn mence *a=*f.*g in scenva n ., r p of*h pT_77_01 p ,. , 1 Section 7.16 for RCS liquid sampling demonstration.
Reason for Deviation: oync.anta PT-??-n1 ene v a,ri e ra n na -av'n-aa A"wi ng MFT. l l
. ,.o r4 V
;g{fgludhuJai""
l Change to Intent of Test: X YES NO Initiated By: [/// -
/4. Date: N J U 6 /.3 r
STE/ TEST DIRECTOR APPROVAL: [ %,- _ Date: HJ7/6 ff SHIFT SUPERVISOR CONCURRENCE: Y bN Date: 7 - / / - 6' 3 LEAD STARTUP ENGINEER / LEVEL IV: //[r/2/'/ te Date: //Julf3 l . ! DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
\
TAB IV ICP-PT-55-02 Test Deficiency Reports TDR # Component Status 679 1RC-8079D Closed . 894 RCP 3 seal leakoff Closed 954 RCP 4 breaker Closed 955 RCP 2 breaker Closed 1270 AFW indication Open 1276 S/G Chemistry Closed 1277 RCS Chemistry Closed 1323 Steam Cenerators Open 1909 Chronological Log Closed g }}{h$Yihi i DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
- ATTACHMENT A CP-SAP-16 Rsvision 6
$ TEST DEFICIENCY REPORT Page 8 of 8
, System Name: Clif/7//C.44 5 l'-/// /MF G J r er c.- TDR No.: Nh J Page ,, ( '
- . y 8 #
Component Tag No: 74)(- fr / c. / )( - c/ c3 c1/ c(/ Safety g
/ of Non-Safety W4' e Startup System No.: 9'/o/ Test Instruction / Procedure No.: PT - 9 9 - c.A DESCRIPTION DE DEELC1ENCT: 7 //E A1c r ;# Tjhic E c /(j 7~ E/2/d 50$ /Uc. A feo 42 d e 4 /r o F S f Z d L) nJ Aea c7str fnn/AA!7 rOc/ /// / 5 #
/. "2 # ,_T l#V LJ+ .f 2.X c e ucle W Ec/7 J~ Pen ~7. f. / 9 &.1 $ "7 C. 3 Component Operation _ _May Not continue until Corrective Action is complete:
CORRECTIVE ACTION: d i _ - /s2 ~ we - , 27, [ wA, s5 # I r (. - PN.
"%Ypyn Sh/7/,.,
'%/g,y REQUIRED RETEST:
Initiated f ,, h ./D f,;l// W Date: V/ /,/ f.$ Engineerir3 Evaluation of Deficiency Required: hYes No Reference Documents for Engineering Evaluation:Ik NMf7 Corrective Action / Retest Approved By: Date: Lead Startup Engineer Corrective Action Completed: Date: System Test Engineer Retest Satisfactorily Completed:
', Scrap Verified By:
System Test Engineer Date: Date: TUGC0 QA Startup/ Turnover Surveillance Supv. l Distributinn: Orieinal rn 'a= Tif 4T ra-4----'-- "- I DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
fa r ca c-s qi Rtvision l [L::i: :ari t4 f..
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f: ;
- g.,7[7 Page 28 or_ 33
( i- t I N 02-07 9
*t '
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3 db ' b ,7p g 9 V6 DATA SHEFT 7 (Page 1 of 2) p,Y ,2,g 3
~\
Seal Water Performance Data Acceptance Indication Description Criter'ia Step 7.6.1 Step 7.6.2 Step 7.6.3 IPIS-140 Seal water injection filter Less than or 141 differential pressure 20 psid 3.6 psid 2,4 psid Z. 3 psid IPIS-175 Seal water return filter Less than gi op 176 differential pressure 20 psid .A psid d.2. psid C .G ysid IFI-145 RCP #1 seal water of 6 67T to injection flow .3 9'gpm , S. 1 spm k T' gpm 9 .~~ spm IFI-144 RCP #2 seal water 3 6 Gr5' to injection flow TP u # gpm .h.6 gpm 7. 7f gpm r e . T gpm 1FI-143 RCP #3 seal water s e Gr3 to injection flow 'f " ; ,3# gpm 8. i spm /.2 3 gpm PO.O gpm IFI-142 RCP #4 seal water 8 injection flow W 3 6#3t'gpm 473~to
- f. Y gpm I. O spa (O .D gpm IFR-157 RCP #1 No. I seal leakoff flow Figure 1 2. / gpm Z.6 gpm '1. 'I spm IFR-156 RCP #2 No. I seal leakoff flow Figure 1 3 I/ gpm 2.9 gpm ?8t gpm
- IFR-155 RCP #3 No. I seal leakoff flow Figure 1 3. 3 gpm 7. . Z. gpm '? .2. gpm 1FR-154 RCP #4 No. I seal leakoff flow Figure 1 '.'l V gpm 'l $ spm 2.3 gpm IPI-153 RCP #1 No. I seal ., o l differential pressure y#g,9b200psid 2 Pc d psid )400 psid 74-C psid j IPI-152 RCP #2 No. I seal
- differential pressure 7
c'
,,,.p2200psid ?v e psid > O O psid >4cn psid i
IPI-151 RCP #3 No. I seal i' differential pressure yf//[f e >200 psid ___ ?> u,- c psid 7 kC2psid 7400 psid i IPI-150 RCP #4 No. I aeal i differential pressure [-([2200 psid ? W Cpsid >4GCpsid M.0c psid 1FIS-194 RCP #1 No. 2 seal leakoff i Neglfgible [/6 %T flow to 0.05 g . . gpm ?$ gpm C . ;b gpm J
~_
/
~ <
, f0R I!!F00u4niv, .... .. .
DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
'. . a. ICP-PT-49-02 f
e
- !FRCE TEST CDPY '
DATA SHEET 7 js%i"- i
, (Page 2 of 2) p 2q3 Seal Water Performance Data Acceptance Indication Description Criteria Step 7.6.1 Steo 7.6.2 Step 7.6.3 171S-193 RCP #2 No. 2 seal leakoff Negligibl flow to 0.05 g C. 1 spm A, A spa 9 2.1 gpm 1FIS-192 RCP #3 No. 2' seal leakoff Negligibi t flow to 0.05 g?m ? . 7f gpm D,3 gpm C. Cf R. gpm IFIS-191 RCP #4 No. 2 seal leakoff NegligibI t flow to 0.05 g: O,.9 spa (8.R 7 spm !
IPI-115 Volume control tank 18 to ~ ~ pressure 60 psig 9O psig 2. E psig~ 2 7_. psig
. +4 p p 1FI-121A Charging flow Info only 7u gpm itT gpm il 5" gpm 7
$f? Y Y s/S.'Usae/
Name/Dat'e N ODice' fk?k hName/Date h.l N A L77 a
/
i L.; i . e l I
~!!;l l
emme l l DATA EXTRACTLD FROM TEST INPROGRESS OR UNDER REVIEW
~. ATTACHMENT A CP-SAP-16 TEST DEFICIENCY REPORT Revision 6 Page 8 of 8 System Name: Aep e re se Coo t ,c u r S vs re m TDR No.: // /
f . Component Tag No: , ~~ _ 7 /3 y- 4cPc pc - o /. o2. o 3 o y Safety Page _ / of _ 7
! Non-Safet) P 't Startup System No.:gecop Test Instruction / Procedure No.:
4 i i Jcp.pr Sr,o9 geg / DESCRIPTION OF DEFICIENCY: _8e /s e n og C e oenu r Mvyfo gg n c g Din Ato r Mcer-jee e prsace 1 A rr ca, renis Atg Aforeo ou 7 >,g. , ( . aesen copie s or Ds ex Snee r- 13 pse e < 99 4 9/ . ns ca _Swe w r 14 Pse rs 92 W9 9 . Ds en hee r 15 psc e- - SHff f* H Ps s e 9 5Y. 9 f. Ano Da rn j Component Operation 1May _ May Not continue until Corrective Action is complete: CORRECTIVE ACTION: kA4ff-- Ac"*ALACE ' ~ Z~AJSPECT ASARCr~ose Am4+w R<. ,o ,$e.ols A< AJK64*fs/A'V [l. , . . . . . . . , . a. t ~~A REQUIRED RETEST: N/[ w A Awec~ r_ eIm-8 '42.2. / /O-9r-S9-n9 Al ! o InitiaNdBy: _ [. / . d Date: 5~/2 /T_3 Engineering Eva uation of Deficiency Required: Yes 7 No Reference Documents for Engineering Evaluation: M. N, Corrective Action / Retest Approved By: p Lead Sca/ tup Engineer Date: 6-NJ Corrective Action Completed:
~
Date: System Test Engineer 3F Retest Satisfactorily Completed: __ Date:
~
System Test Engineer Scrap Verified By: TUGCO QA Startup/ Turnover Surveillance Sunu
*ste:
~
R ED FR TEST INPROGRESS OR UNDER REVIEW
= . ..
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h hI r@s:/ I. q 1CP-PT-55-09 Revision 1 bY$l Nb 3b j Uh Page 89 of 124 04-04-83 (h DATA SHEET 13 17)A 0 lllY REACTOR COOLANT PUMP 1-1 Pr '5' ' Performance at 1400 psig Descriotion Ins crument Location namel RCS Pressure Criteria Data Units Date f.gg , 1350 to 1450 g. psig
,,,.y
-s-
- Hot Leg 1 Temp T'413A Computer T0419A N/A *F g ..s W . -
Cold Leg i Temp 'E ES. ~4 6 - 1. Y 4 T'4133 Computer N/A 435 (r
- F j
.e. '.A T0406A RCS Loop 1 Flow F'414 Computer
- 2. 14 a N/A % p.Sc..ed.
70400A f o E fc RCS Losp 1 Flow F'415 Computer 62M N/A 1 t<.-M RCS Loop'l Flow F0401A l C CI A 9' 4 2 t .; F'i16 Computer N/A % p# 2 5.a- M t-
- ic
70402A I O 8: O
No. 1 Seal Water F'145 Computer 2
Injeecion Flow 6 (Min) GPM '*"I/> + ~ VCT Outlet Temp T'110 F0131A 13 (Max) 8 74 e/> /< 7 Computer *F -, T0140A 130(max) I C / (- ;. -ch e p/r4 Charging Pump 1-FI-120A IC3-06 N/A - psig w w-Disch. Header Pressure
'F A-D No. 1 Seal Watee 1-FIS-165 Local N/A Bvoass Flow GPM
**O #. "
)TDR. No. 1 Seal Water 1-FR-157 1-CS-05 for. w -
,- l.-
Leakoff Flow bee 1Figury',',S, 9PM No. 1 Seal Water 1-PI-184 (Y J - 4 > /i Local N/A Leakoff Pressure N psig f.:,4/9 i .T./; % A No. 1 Seal Water 1-PI-153A 1-C3-05 Leakoff /Bvoass Diff P 200
- Sin) . P S ID -. . i-No. 1 Seal Water 2470 (Msx)'- N d *-es '
1-II-174 Return Header Temo 60 (Min) *F ..ic.+ - local 235 (Max) ?$- ' cT /r 3 No. 2 Seal Water 1-FIS-194 0.05 , GPM e. M -.- -- ' Leakoff Flow Local (Nor=al) '6 I -
<- .' .*'3 Seal Injection 1-PIS-140/or Local -
Filter Diff P L=2;S-41 20 (ca:) PSID # . 7./. ,, Seal Water Heat Y. 6 Sh /< 3, 1-II-177 'F y r b,h-Exch. Cutlet Temo Local 130 (max) ~7 7 ch /*3 RD'. ARKS : O ra.: n - .<- ..n - . . . - 'd * ~ ' . r- ." r'- . -- '
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~
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- DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
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?) 1CP-PT-55-09 lW. k; f';g f)
M e [ Revision 1 1 N.: Q E] } 4 W,(!Clu l' JQlI '.i,,. b=v
' " Page 92 of 124 04-04-83 (h
DATA SHEET 14
;pg / llI!/
7 REACTOR COOLANT PUMP 1-2 Performance at 1400 psig Name/ Descriotion Instrument Location Criteria Data Units Date
. ;3gy 1,:. i < . . -
i RCS Pressure N - M' ~C 6 _M5tTeo 1450 /d'Cesig .c k O Hot Lag 2 Temp 7/T $~ T ' 423 A Computer N/A - F p T;Cmi-T0439A W 4.0 e/> /c ; l Cold Leg 2 Temp T'4233 Computer N/A F T0426A C V. C 97f;h
-- N 7c ~5 RCS Loop 2 Flow F'424 Computer
~
n'r/3M-% F0420A N/A // 3. '/ % I e/4 /e3. l RCS Loop 2 Flow F'425 Computer
;r jM - -
,. F0421A N/A //7.7 % p<h /(- 3
~
RCS Loop 2 Flow F'426 Computer ..';~~ A A - _
/
No. 1 Seal Water F'144 F0422A N/A ///.l % </2h.3 Computtr 6(Min) GPM e ;r-f3c,.g Iniection Flev F012 M 13(Max) 7 / ?' VCI Outlet Temp I* </2 /(-3 I'116 Computer F T0140A 130(max) /c0 V II.. /A. sf T/t*3 Charging Pump 1-PI-120A psig.;W (<.- M Disch. Header Pressure 1-C3-06 N/A Ill.CO s. 2 t 3 No. 1 S.yal Water 1-FIS-164 , w , 4-. Bveass Flow Local N/A O. 4 GPM <. o _ g 7 D R. No.1 Seal Water 1-FR-156 1-C3-05 See Figure,7 GPMc;f,Jc gd Leakoff Flov No. 1 Seal Water 1-PI-184 1 (O %. 2.n
.g;. p i Leakoff Pressure Local N/A
' osie <C.'.e-l No.1 Seal Water 1-PI-152A 1-C3-05 200(Min) PSID M u @ ,
Leakoff /Bvoass Diff P 2470(Max)4- O O V 4 . z . s. , No. 1 Seal Water 1-II-174 c0(Min) F w.6 Return Header Temo Local 23 5 (.ax) M 9-1a?> No. 2 Seal Water 1-FIS-193 (. , aJ,v n. m-Leakoff Flow Local 0.05(NormalT7 CPM -T ~ -;'? l Seal Injection 1-PIS-140/or. . Local 20(Max) PSID ;,t. yC Filter Diff P '. " ' 0 - ; !. '. TD '.M c; ..s o Seal Water Heat 1-II-177 'F i - Exch. Outlet Temo Local --f2 130(max) ~"Ci'Ff REMARKS: @ h .-, m A- o:>Se .m- N ' ~~~ - + ' / . '
- c. . * ~
Pump-4 tarted hours /seopped -houes - -- - T P D Reviewed 3y: Date: w e,
.3 ,
DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
9 .* ee g ICP-PT-55-09 I l.L jOr .0 Tb F,F \sr.We Revision 1
*. L
.I ' (' b' C d k*
i
- t! '
'j fiW'A !!G h US ' " [t j =6 Page 94 of 124 04-04-83
- d. U+ U ;rgg$1)/ /
() DATA SHEET 14 (Continued) 7 REACTOR COOLANT PUFCP 1-2 Performance at 1400 psig Name/ Descriotion Instrument Location Criteria Data Units Date , Motor Voltage A-B :. s ,4.,-- Bus 1A2 5940 (Min) g.p. Volts -/ . c ;- -- ,
.: t, .- .
7260 (Max) 2 o, Motor Voltage B-C Bus 1A2 5940 (Min) c.c. Volts
. vi. , n-7260 (Max) ~- r '? '
Motor Voltage C-A Bus 1A2 5940 (Min) Volts ,;,. 7 :d g . ,. 7260 (Max) 1' 0 ife Motor Current A j Bus 1A2 755 (Max) -J b Amps / 'i a r - - Cubicle 8 9.2-0 Motor Current B Bus 1A2 755 (Max) 9' % Amps v4 ~7M-Cubicle 8 6 .-Y3 Motor Current C Bus 1A2 755 (Max) (7.g Amps w f.'j- A-1 Cubicle 8 <- o .u3 Vibration - Vertical Ben-Nev 1-CV-07 15 (Max) Mils a h C E. D l u . k .9.z Vibration - Horiz. Ben-Nev 1-CV-07 15 (Max) b* Mils '8ru.'.A S O.vg -4 Coastdown Time Stoowatch Local N/A min /see DA No.3 Seal , 400(min) ) p/3h
' Injection Volume Local 1600(max)f /WJC/hr ch 4 3 No. 3 Seal Leakoff Volume Collected Local 800(cax) ?(- CC/hr', e-n gg Remarks: .
Reviewed By: Date: 7~s 7 s ,vorwid ;- c -r M T*E - / 74 - O n r,:- Csg 14 Si? S 3 STcs' .wWcif M rg- 232 i ca:L OvG c& cfE3 (~ t.co ; t-17E -It 5 g OME CCE f 5 Je t- 23 I n.. - i c. ll lidiutthballdi$ bd )= .
**e g" e e e shal. y e. . ens e e em- em e e ese e . m== e DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
d I 1CP-PT-55-09 i 33*, %. b I by Mfirc 5 23 g g ,fr Revision 1 )
.' I ,
Page 95 of 124
- gp//7 gj
' i 3 3 L J L ,. ]d - if . c 1
() DATA SHEET 15 l REACTOR COOLANT PUMP 1-3 Performance at 1400 psig / g/p (/
&} j Name/ i Descriotion Instrument _ Location Criteria Data Units Date l RCS Pressure ,.ca vg 1350 to 1450 p s ig -.u. iw-.
, , . g. 9 g/g
.t. .y3 i Hot Leg 3 Temp T'433A Computer N/A 'F u.Tr. %
T0459A 435 9 ' - /.* / ' ' [ Cold Leg 3 Temp T'4338 Computer N/A
- F p. T.t.A .
T0446A Ll3 Q. ( f, /o a r RCS Loop 3 Flow F'434 Computer F440A N/A i W C' % b'.h 7, /.* 3/;,-.'~ RCS Loop 3 Flow F'435 Computer F441A N/A is I.O % p.:; S) /c'.5/Js% RCS Loop 3 Flow F'436 Computer a f /.W% F442A N/A Ico r, % / (4/ No. 1 Seal Water Computer 6(Min) GPM .fk,M c .. % L Injection Flow F'143 F0127A 13(Max) 767 I F4./M L VCT Outlet Temp T' 116 Computer F 2. D .res- a l T0140A 130(max) T( '/ ' /s h
- I Charging Pump Disc. 1-PI-120A 1-C3-06 N/A j '< ' . . psig m h -.- -
Header Pressure ' ' - l !? L No. 1 Seal Water 1-FIS-163 GPM -i..<- Bvoass Flow Local N/A U' 0 1fD/t, No.1 c. 2. 93 Seal Water 1-FR-155 1-C3-05 See Fig. (ff,o )GPM
-w a Leekoff Flow 1 ; :r- p 33 No. 1 Seal Water 1-PI-184 psig ru. 7.-d Leakoff Pressure Local N/A M,, f".A-.73 No. 1 Seal Water 1-PI-151A 1-C3-05 200(Min) ... psid n r . .~ ---. -
Leakoff /Bvoass Diff P 2470(Max) - " 6) .r . 2 .v.- No. 2 Seal Water 1-II-174 60(Min) F -m. - <w Return Header Temo 1-FIS-192 Local 235(Max) N t. . gJ No. 2 Seal Water 0.05 _/ , l Leakoff Flow Local (Mormal) ( " .J'JO'. GPM - ..:...,- . --
- Seal Injection 1-PIS-140/or, ,,,yi. 20 (Max) psid .m . < %
Filter Diff P 1 ? M !" Local
,6
- s. 5.2.py Seal Water Heat 1-TI-177 *F -e. . v c I
Exchancer Outlet Temo Local 130 (Max) ~7.'2 c..g.p; REMARKS: 6 .3.c - :- a .. v (. 3 ' -:: ' ' ** J
/
' ..,Stsreed hours /-steppe; hour. --
---qf'dD Reviewed By: Date:
3 -
.m \Lii....a A u2 L, ._ _ : -.-. - . . - - . - - - - - - - . . - - - - ----
DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
- - ._ L- - - -.:.-_-. .-
a _w, w g' b. y : p;- g, ICP-PT-55-09
E' .,c F.i- (.' I , .y .I,t!)
Ii,! Y!2OT f.pl.' Ii N.'./,, Revision 1 g {# ': { u D1 CL j M'f Q '2 '*%, ig (gl Page 98 of 124
'1 S g.,' 04-04 DATA SHEET 16 REACTOR COOLANT PUMP 1-4 7 Performance at 1400 psig Descriotion Instrument Name/
RCS Prsssure Location Criteria
. . p . ,.; ,, Data Units Date
.. . . , .c.3 . g, 1350 to 1450 j g,; psig -m.7--
1 Hot Leg 4 Temp T'443A Computer
-i
.A N/A
- F p./.uv 6 .c. -
T0479A #/3C f Cold Leg 4 Temp T'443B ah A 3 Computer N/A T0466A '
'F r /,j,,#~
RCS Loop 4 Flow F'444 '// T C' ' c h h =. Computer . RCS Loop 4 Flow F0460A N/A
- 7 /34 - -
2 . F'445 Computer //1.7 % I <% /c 3 RCS Loop 4 Flow F0461A N/A / / S' .2. % 75 - ab% F'446 Com7 uter r/r 7s* 3 F04!2A * ' Z O c:+ - - -- No. 1 Seal Water Computer N/A ///.O % r/2 /(- 9 , Iniection Flow F'142 F0125A 6(Min) GPM .yg .r /1 VCT Outlet remp T' 116 Computer 13(Max) #/ /T Ie/MP3
*F -*
Charging Pump Disc. 1-PI-120A ~ T0140A m'- 130(Max) SM . 7 N/A b./.7/ ._/., W ~ t Hender Pressure I U C4 ', - ~. psig m .,- g s
)PDA No. 1 Seal Water No. 1 Seal Water Bvoass Flow 1-FIS-162 1-FR-154 Local N/A O' O. GPM s ~ .2.'
-m. .s .%
F" 9
'TPDF 1-CB-05 See Fig.
Leakoff Flow GPM ,~ . wA No. 1 Seal Water 1-PI-18's 1 O'M .s ' 2 . - ! Leakoff Pressure psig ( Local N/A d p.T. /3 No. 1 Seal Water 1-PL-150A 1-C3-05 c / / r- 5 Leakoff /Bvoass Diff P 200(Min) i ps2.d rw-No. 2 Seal Water 1-TI-174 2470fMax) C1 ' ' ^ ~C Return Header Temo 60 (Min) F t .T tj,-.=w No. 2 Seal Water 1-FIS-191 Local 23S(Max) ?[. j .r/. / e ; Leakoff Flow 0.05 f,,l.GPM 3 ;, ; Local (No r=al) '--"'I . ~)? Seal Injection 1-PIS-140/or < . - J ,'! Filter Diff P l-PIS-141 Local 20(Max) 36 psid 7 7 /.We Seal Water Heat 1-II-177 Ch. / (-5 _ Exchanger outlet Temo 'F <7 - Local 130(Max) 7A I .e/r / a.-
/ P3 REMARKS: $ ,. u . .i .hb u.e J . u . ..? c. . - - S _. , J Reviewed By:
l Date: l l I
) . M i,,,a..
g *"%..ww u k i . . .. i
] DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
- ~ = = - - . - - - _ . - -
l
, . * , ATTACRMEUT A CP-SAP-16 Revision 6
.f. . ,,.,
TEST DEFICIENCY REPORT Page 8 of 8 J' s System Name: Reactor Coolant TDR No. : 79
+
Component Tag No: TBX-RCPCPX-03 Page_ 1 of 1 Safety
% - Non-Safety {
Startup System No.: 55 Test Instruction / Procedure No.:1-CP-PT-55-02 DESCRIPTION OF DEFlCIENCY:RCP3 #1 seal leakoff flow is greater than the allowed setpoint of 5.7 spm when the #1 seal is unisolated. RCP #3 i was secured when #1 seal leakoff flow of 5.7 gpm was reached while 4 increasing RCS pressure from 400 psig to 1400 psig on March 18,1983, i in accordance with Westinghouse Memo TBX-M-1005 of March 15,1983, from R.L.Moller. 1
+
Component Operation _May X_May Not continue until Corrective Action is complete:
- CORRECTIVE ACTION: Reseat seal or replace the seal.Pume uv be noerme.A as long as #1 seal leak-off is below 5.7 enm.
I-f
~
tUR IV0RWTE XY i REQUIRED RETEST: With #1 seal leakoff below 5.7 apm. hand rotate the pump, and then run pump in accordance with IPO-001A. Initiated By: 44 / c- ._ Date: 2-/9-TG j Engineering Evaluation of Deficiency Required: Yes X No l Reference Documents for Engineering Evaluat on: / M /A ! Corrective Action / Retest Approved By: Date:.I-N"'87 Corrective Action Completed: A 1A W h{(f.eadStartu$ Engineer Date:7 / b h
's ' egm est Engineer
' Retest Satisfactorily Co=pleta9. n l bA_ Date: , - T -b ys em Test Engincer Scrap Verified By: ii k Date:
TUGC0 QA Startup/(Turnover Surveillance Supv. Distriburinna -oe4aia=1 Pa iaa "T *""'"**"'- "" DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
~
As iAcw1u.* A c < .,,a - m e 'N 'd Revision 6
' \-
TEST DEFICIENCY REPORT Pcgs 8 of 8 9 ... System Name: RC 'S Page / _ of / Component Tag No: Cet-t90 N S_-os 8pR44 Safety Non-Safety { Startup System No.: If01 Test Instruction / Procedure No.: X&-KF-/v DESCRIPTION OF DEFICIENCY: We-,A kep %.s p h e e ,$ Aecs 4 we J k ,ack octue
%% a< u%$ ~%s e ana <t . A}mA bl<L Yt G. udM ( A?? O O D Id W (. ' '
U 6 V m w 4 won IA .,,d au. la -L cm.A ai,,o ao.a . i <J Component Operation _May _t May Not continue until Corrective Action is complete: CORRECTIVE ACTION: Reh p ts NS',o o hamh
- u ,1 o,ut b tid 1
% 4:. 98'1
... - m m n @E g wu--
QUIRED RETEST: [ed..,_ w ,2./ E o.) A pbcewh [Re. be.c pw ' Initiated By: \l/sb/h5 Date: pM -s 3, Engineering Evaluation of Deficiency Required: ]Yes o Reference Documents for Engineering Evaluation: / Corrective Action / Retest Approved By: Date: M*"8['d.[ Start'up Enginear
~
Corrective Action Completed: _yS) [
- Date: 7-/-ff seggineer Retest Satisfactorily Completed: s/El Date: 7 - f -&f stem est Engineer Scrap Verified By: A Date: n/4 TUCCO QA Startup/Tdrnover Surveillance Supv.
Distribution: Original to Log TUSI Engineering Manager _ DATA _ EXTRACTED _EROM TEST _lNPROGRESS OR UNDER REVIEW
ATTACHME:;T A CP-SAP-16
- Rcvision 6
/ -
TEST DEFICIENCY REPORT Page 8 of 8 TDR No. : 9 fy-System Name: Reactor Coolant Page 1 of lM&hty,3 Safety Non-Safety [ + Component Tag No: 1/1-PCPX-4 (RCP#4 breaker) s} Startup System No.: 55 Test Instruction / Procedure No.: PT-55-02 DESCRIPTION OF DEFICIENCY: During the venting of the reactor coolant system per PT-55-02 Step 7.1.10 with RCP#4 and RCPf3 running, RCP#2 was started and RCP!4 tripped immediately thereafter. The trip was due to B phase instantaneous current and C phase overcurrent. ~ f0s siihiiMilM WLY X Component Operation _May _May Not continue until Corrective Action is complete: CORRECTIVE ACTION: Troublenhner 2-d enr-ore eko e m,, ee nr ek. 4e r 4,4 n r., the nynki n- use n4nen4ne A en km -kse Pha n i et ,i n (770 nmne) n# ehe *4-o nwave,,v-ma* Mn V1 91 vol se use co* enn einem en the enl a lenn romerne nn-n enter rho i na,, r ei nn A 4 =le nf cho=. nyerentrene reinvs will v,. n4ng e.ivvene (ARA s-net. vocoe nn1v uhon eho enveen* 4e le== eknn A M nf ninkun (Al? nang). The induction di ete unnla *nrn on mneer nenreing 9mes (neerev. 3000 ames) but would not reset when the motor reiched runnine current. Startine ancther reactor collant Dumo motor on REQUIRED RETEST: XCP-EE-3 on 50M1-51 0.C. reinvm of each RCP. Initiated By: [ /{/ Date: 8eM8ME Y' Engineerins Evaluation of Deficiency Required: ]Yes ] No Reference Docu=ents for Engineering Evaluation: / Corrective Action / Retest Approved By . '..g Date: //-83 4.ead startup Engi der Corrective Action Co pleted: ggM Date: VMMr
" W fst6: Test Engineer .
2etest Satisfactorily Completed: /8w Date: ud-45 6 S7s5 4m Test,. Engineer
~' v /p Date:
Scrap Verified By: TUGC0 QA Startup/Iurno9er Surveillance Sup e.
. c. ~ .
DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
,. 7,, s ~
TDR No. Y N CP-SAP-1,6 .
~* q Revision 6 s J . Page 2 of 2 Corrective Action:(Cont'd from page 1) the same transformer winding, which caused reduced bus voltage and increased running current.on the motor already running, would cause the induction disk to time out and trip the motor already running. New settings were made as temporary modifications and a permanent change was requested by memo SU-83165. Subsequent running of the RCP's was satisfactory.
FOR mv Illiwo, ear.a,l gp
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'#e g 'M' . DATA EXTRAC]D FROM TEST INPROGRESS OR U
~ -
ATTACRMENT A CP-SAP-16 TEST DEFICIENCY REPORT Revision 6
,' Page 8 of 8
- System Name: _ RCS TDR No.: h#
Component Tag No: 1/1-PCP X 2 Pa
' o f _1 Startup System No.:_ 55 Safety {ge_1Non-Safetyg Test Instruction / Procedure No.: 1-CP-PT-55-02 DESCRIPTION OF DEFICIENCY:
While preforming step 7.1.10 on page 25, the RCP _bremkar for #2 RCP trioned a few seconds af ter closing. The breaker was vi mm11v inanected and no oroblems were evident. Relay devices 50MI-51 and 26 had A Phane and C Phase tarrets respective 1v. These targets were reset. _Anneny ? hnurn and 30 minutes after the first start, a second start was attempted. The breaker trieeed aceroximatelv 10 seconds after closing. Breaker again u== vinum11v inseeeted and device 26 Phase A flag was dropped relay calibratio n
.of the 90m -51 and 26 devices was verified. A third try was attempted approx 3
- Component hours afterOperation the second 1 Maytry. The 3rd try was successful-no trips.
_ May Not continue until Corrective Action is complete: CORRECTIVE ACTION: Troubleshoot and correct the cause of the defis?.*acy. () Investication revealed that some of the O.C. relay induction disks were not resettine due to dust and filing caucht between the permanent magnet and the disk. All the O.C. relavs were cleaned to alleviate this problem. It was also determined tha t the 50M1-51 0.C. ralav pickup setting _.was-too. close-to -the - RCP cold loco runnine current. New settinas were made as ::emporary modification. and n eermanent chance was recuested by Memo SU-83165. RCP's was satisfactory. Subsecuent running of the REQUIRED RETEST: _,__ JCP-EE-3 on 50M1-51 0.C. relavs for each RCP.
/7 A Initiated B . ^ m
[ l
/ -
Date: 2 -d " b Engineering valuation of Deficiency Required: - geg t ]Yes {No Reference Documents for Engineering Evaluation: #/M Corrective Action / Retest Approved B l __ A Corrective Action Completed: , / Lead Startup Eng eer ~ Date: -WD
. -w Date: v/$M 3 $"
Retest Satisfactorily Completed:" Aiys [ fem+<--- I sEngineer - CD Date: vM'[/-3 Scrap Verified By: Sylic'fxf T(se Engineer % Al 4 M TUGCO QA Startup/ Turnover Surveillance Supv. Date: __A/A' Distribution: Oriefnal en T.a. t"ev e--'- -
* *e *y e DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
ATTAC101ENI A CP-SAP-16
. Revision 6 TEST DEFICIENCY REPORT Page 8 of 8 TDR No. : /8C0 System Name: [ tad #4 (Q h Component Tag No: Nd' 8d/6/d-O3 _ s,,fety Non-Safety Startup System No.: I k Test Instruction / Procedure No.: Aj/A DESCRIPTION OF DEFICIENCY: 7(M 7N/ s2/dtk df) DEL ###
uL'ad Altattd dMC/ MCS at 450F//000 & ,/ / u9ahzet atas vnKtd sin ik 7to3 m?'a$<'Ine6fy 4 aYuwku . Q A h k u k a 2 a 22 t id u # M U $ 3
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Q ComponentOperation,(May _ May Not continue until Corrective Action is cceplete: CORRECTIVE ACTION: .)[4' TB8 4/y,
/ // ,/
V
. .a
, >WRh g guw -
REQUIRED RETEST: Mg 7"8g. A)d, /// / \ Init d By: /2 /J , Date: cd/UA//3
"/
i ! Engineering Evaluation of Deficiency Required: ]Yes { No Reference Docucents for Engineering Evaluation: " Carrective Action /Reces't Approved By: Date: #['df'bl l Lead Startug Engineer Cerrective Action Completed: Date: System Test Engineer Retest Satisfactorily Cacpleted: Date: [ System Test Engineer l .. Date: V Scrap \'crified By: l TCGCu UA Startc.p/Tt:rno rar :.urveill: ace Supv. l I l Distribu:icn: C ri;inal tc Log TUSI Engineering Mar.ager rvaillar:e Supe-viscr Initiatip, STE TyGCO QA Startup/Turnove ( . ., . 1 ; DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
, . ATTACHMENT A
. C? CA?-16 Ravision 6 TEST DEFI!IENCY REPORT Page 8 of 8 Systen Name: b b ig f1Zd/'/EtY b " **' -
Compenent Tag No: f/44 e6 mad /2[e: L Safety Non-Saf y
'(. Startup System No.: 37 Test Instruction /P ccedure No.: f/-/T~66"Od-DESCRIPTION OF DEFICIENCY: St#/i/lf v' M N /d M M M
(/ u slathern mact (PT-5s'oa i .do n a)rAe u ->446ubw . mod (s v-I. /LI-awf6 (csr.auf) .ned 0# auhd m' '/0,4& 6/ Q. IFz-dM$ (M<).,Ns'w6 v sk4) nee %8d itLN45r1. (04506/~A y v
- 3. IHS-dy54FT {Afk).,w/mp i < /vmini/Aar) u <
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< v LJ l< r-50!A (sh I vR svel).,aeseed.d44 +ieM aud pofd
- cc 6l V(/ t/
5 /t r-50JA (S/6 A wR .hexf) ctsned JAd ) .eisec&
< c/y' e' Co=ponentOpera: ion [May _ May Not con:inue un:il Corre::ive Ac: ion is ec=plete:
CCRRECTIVE ACTION:
/ ??/d C llI~ AY'ISb n2df/ COMtk.
R. w wedauf emke v JY/Fr-dM6
- t. 3. YkAe iHs-aci56fr ~sp.,,."4x.6/ ecd.
y &dkg Il..Z~~ F O /A &/d e W*/ W ij. t. jw , , , . [ &g / t. Z - $ 0 ) A A u g g srygg & a " Ul'h L s tir'd U RIOUIF.ED RETIE!: d M7/4[d/ Oict/? //tcd' ,/ M 4$ d444444
. ~ i U
mal/ .-!.4?d/Cd/.20?G -
/
Ini:iated By: /[ I' /Le Date: 4:T/>Mvf.3 l Y Engineering Evaluation of Deficiency Required: Yes { So
?.aference Docu=ents for Engineering Evaluation: ,
- Carrec:ive Ac:icn/ Rete.[c Approved By: +s- .</
Lead Stn:6p Engineer Date: ~
.[
Cc ree:ive Ac:ica C pleted:
~
Da:e: Syste= Tes: Engineer Reces: Sa:isfae:::11y Cc:ple:ed: Da:e: Sys:a: !*s: En;ineer 5::t; Vcrified Ey: I Ds:e: l !!*GC0 OA 5:::: p/ Turnover :sc veillance Supv. _ Lis: ibu:icn: Ori;inal to Leg Tl*3I En;'..* eering Manaser s,c,rn m e......--. DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
~
, ATTACHMENT A CP-SAP-16
- 5. . -
Revision 6
,5 TEST DEFICIENCY REPORT Page 8 of 8
-System Name: Rea'etor Coolant TDR No.: ; O "") 6
( Component Tag No: TRWROPCh01 O?.O'!. and 04 Safety Page l _ of Non-Safety G Startup System No.: ssol Test Instruction / Procedure No.: ICP-PT-55-02 DESCRIPTION OF DEFICIENCY: nurfne kne funee4nn21 recefne che neemm eenerator chemistry analyses showed some out of specification results (see attached
, data). The major problems concerned pH, cation conductivity, and silica.
The pH control problems were due to: (1) an initial wet layup high pH which decreased slowly due to low steaming rates, and (2) later batch additions of hydrazine, combined with low steaming rates, caused sharp swings in pH. Cation conductivity and silica were initially high since this was the first heacup of the generators to their normal operating temperature (see page 2) 4 Component Operation ,X_May __May Not continue until Corrective Action is cceplete: CORRE TIVE ACTION: None required. As the attached graphs show, the steam generator chemistry was gradually improved during the HFT by steam generator i.
\
blowdown and condensate polishing systems.
..,,-.g.
kdOhl[ mod b8 REQUIRED RETEST: None required. i Init ted By: /d, Date: OSTA).f.f 7 Engineering Evaluation of Deficiency Required: Ov-y, Esa Reference Documents for Engineerina Evaluation: , FsO .
~'
Corrective Action /Re st Approved By: Date: Lead.Jeajf up Engineer Corrective Acrion Completed: ////29//A > Date: U7dAl/./ Retest Satisfactorily Completed: Syst9m AJ/A TWef.:f[ieinjer#// ///A., Date:077UAl/3 h ,/ Sysi:em Tes/ 2.ngineer > l Scrap Verified By: A//4 Date: A TL*GCC OA iftartu:;!crnover Surveillance Sur7 ' DATA EXTRACTED FR TEST INPROGRESS OR UNDER REVIEW
I TDR No.: fcP 7 // Page e2. ofg DESCRIPTION OF DEFICIENCY (Cont'd) and the expected release of fabrication / construction contaminants was noted. Other parameters, not displayed on the graphs, which were out of specification: Steam Generator,f,1 Steam Generator #4 1400/08 Mar Dissolved oxygen (0 ) 15 ppb 0230/19 Mar 0 Sppb 2 0740/10 Mar Chloride (C1) 0.18 ppm 2 0700/11 Mar C1 0.2 ppm 1010/06May 0 Sppb 1430/14 Mar 0 5 ppb 2 , 2 1830/12May 0 Sppb 0845/01May 0 Sppb 2 2 0959/24May 0 5 ppb 1004/08May 0210 ppb 2 0930/26May 0 300 ppb 1930/12May 0 10 ppb 2 2 0959/24May 0 Sppb 2 0930/26May 0 15 ppb 2 Steam Generator #2 1400/08 Mar 0 15 ppb 2 k 1010/06May 0 .15 ppb 2 0814/20May 0 Sppb 2 Steam Generator 13
, 1400/08 Mar 0 20 ppb 2
l 0700/11 Mar Sodium (Na) 0.17 ppm 0200/21 Mar 0 Sppb 2 0845/22 Mar Cl 0.2 ppm i Ii 4 - l 0216/02Apr Na 0.14 ppm 1010/05May 0 5 ppb 2 1830/12May 0 5 ppb 2 0950/13May Na 0.2 ppm ) 0930/26May Na 0.11 ppm and 0 100 ppb 2 i l s In addition, the. suspended solids analysis was out of specification on all stea= generators periodically, However, due to pluggiag of the process [ sampling system components, it was determined tsat suspended solids analysis would be inaccurate. This problem has been forwarded to Er. :aaerin:: via DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
~
' TDR ,No.: Id 70 Page 3 of /3 i
s ") The steaming specification for steam generator chemistry during hot functional testing was as follevs: 4 pH 8.8 to 9.2 Chloride Less than 0.15 ppm Hydrazine N/A Cation conductivity Less than 2.0 umho/cm Sodium Less than 0.1 ppm Ammonia 0.5 ppm, maximum Dissolved oxygen Less than 5 ppb Silica Less than 1.0 ppm Suspended solids Less than 1.0 ppm () f0?E0iddi,iiG;,g.y
)
l ! . s. - t . !' DATA EXTRACTED FROM TEST INPROGRESS OR UNDER REVIEW
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